subject:(Nuclear fusion)

1. Fiorucci, Donatella. Étude de faisabilité d'un résonateur optique pour des applications aux systèmes d'injection de neutres pour la prochaine génération de réacteurs à fusion nucléaire : Feasibility study of an optical resonator for applications in neutral-beam injection systems for the next generation of nuclear fusion reactors.

Degree: Docteur es, Physique, 2015, Nice

URL: http://www.theses.fr/2015NICE4026

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Cette étude fait partie d'un projet plus large appelé SIPHORE (SIngle gap PHOtoneutralizer energy REcovery injector), visant à améliorer l'efficacité globale de l'un des mécanismes… (more)

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Cette étude fait partie d'un projet plus large appelé SIPHORE (SIngle gap PHOtoneutralizer energy REcovery injector), visant à améliorer l'efficacité globale de l'un des mécanismes par lesquels le plasma est chauffe, dans un réacteur de fusion nucléaire, à savoir le système d'injection de neutres (IDN). Une composante importante d'un système IDN est le neutraliseur de faisceaux d'ions de haute énergie. SIPHORE propose de substituer le neutraliseur à cellule à gaz, utilisé dans les systèmes IDN actuels, par un photo-neutraliseur exploitant le processus de photo-détachement dans des cavités Fabry Perot. Ce mécanisme devrait permettre une efficacité globale η> 60% du système IDN, nettement plus élevée que celle actuellement possible (η <25% pour ITER). Le travail de thèse porte sur l'étude de faisabilité d'une cavité optique avec des propriétés adaptées aux systèmes IDN. Dans ce contexte, le problème de la détermination d'une conception de la cavité optique appropriée a été tout d'abord pris en considération et l'analyse théorique ainsi qu'expérimentale d'un résonateur optique ont été effectuées. Les problèmes lies aux niveaux élevés de puissance optique intracavité (~3 MW) nécessaire pour un taux de photo-neutralisation adéquat ont ensuite été prises en compte. A cet égard, nous avons traite a la fois le problème des effets thermiques sur les miroirs de la cavité en raison de leur absorption de la puissance optique intra-cavite (~1 W) et celui associe à la nécessité d'un faisceau laser d'entrée de puissance élevée (~1 kW) pour alimenter le résonateur optique.

This work is part of a larger project called SIPHORE (SIngle gap PHOtoneutralizer energy RE-covery injector), which aims to enhance the overall efficiency of one of the mechanisms through which the plasma is heated, in a nuclear fusion reactor, i.e. the Neutral Beam Injection (NBI) system. An important component of a NBI system is the neutralizer of high energetic ion beams. SIPHORE proposes to substitute the gas cell neutralizer, used in the current NBI systems, with a photo-neutralizer exploiting the photo-detachment process within Fabry Perot cavities. This mechanism should allow a relevant NBI global efficiency of η> 60%, significantly higher than the one currently possible (η<25% for ITER). The present work concerns the feasibility study of an optical cavity with suitable properties for applications in NBI systems. Within this context, the issue of the determination of an appropriated optical cavity design has been firstly considered and the theoretical and experimental analysis of a particular optical resonator has been carried on. The problems associated with the high levels of intracavity optical power (~3 MW) required for an adequate photo-neutralization rate have then been faced. In this respect, we addressed both the problem of the thermal effects on the cavity mirrors due to their absorption of intra-cavity optical power (~1W) and the one associated to the necessity of a high powerful input laser beam (~1 kW) to feed the optical resonator.

Advisors/Committee Members: Man, Catherine Nary (thesis director).

Subjects/Keywords: Fusion nucléaire; Réacteurs nucléaires; Nuclear fusion reactors

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APA (6^th Edition):

Fiorucci, D. (2015). Étude de faisabilité d'un résonateur optique pour des applications aux systèmes d'injection de neutres pour la prochaine génération de réacteurs à fusion nucléaire : Feasibility study of an optical resonator for applications in neutral-beam injection systems for the next generation of nuclear fusion reactors. (Doctoral Dissertation). Nice. Retrieved from http://www.theses.fr/2015NICE4026

Chicago Manual of Style (16^th Edition):

Fiorucci, Donatella. “Étude de faisabilité d'un résonateur optique pour des applications aux systèmes d'injection de neutres pour la prochaine génération de réacteurs à fusion nucléaire : Feasibility study of an optical resonator for applications in neutral-beam injection systems for the next generation of nuclear fusion reactors.” 2015. Doctoral Dissertation, Nice. Accessed April 11, 2021. http://www.theses.fr/2015NICE4026.

MLA Handbook (7^th Edition):

Fiorucci, Donatella. “Étude de faisabilité d'un résonateur optique pour des applications aux systèmes d'injection de neutres pour la prochaine génération de réacteurs à fusion nucléaire : Feasibility study of an optical resonator for applications in neutral-beam injection systems for the next generation of nuclear fusion reactors.” 2015. Web. 11 Apr 2021.

Vancouver:

Fiorucci D. Étude de faisabilité d'un résonateur optique pour des applications aux systèmes d'injection de neutres pour la prochaine génération de réacteurs à fusion nucléaire : Feasibility study of an optical resonator for applications in neutral-beam injection systems for the next generation of nuclear fusion reactors. [Internet] [Doctoral dissertation]. Nice; 2015. [cited 2021 Apr 11]. Available from: http://www.theses.fr/2015NICE4026.

Council of Science Editors:

Fiorucci D. Étude de faisabilité d'un résonateur optique pour des applications aux systèmes d'injection de neutres pour la prochaine génération de réacteurs à fusion nucléaire : Feasibility study of an optical resonator for applications in neutral-beam injection systems for the next generation of nuclear fusion reactors. [Doctoral Dissertation]. Nice; 2015. Available from: http://www.theses.fr/2015NICE4026

University of Manchester

2. Khan, Aneeqa. ANALYSIS AND EFFECTS OF FUSION RELEVANT DAMAGE IN TUNGSTEN.

Degree: 2017, University of Manchester

URL: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:309815

► Tungsten is a candidate material for plasma facing components in the experimental fusion reactor, ITER and the demonstration fusion reactor, DEMO. It has been chosen… (more)

▼ Tungsten is a candidate material for plasma facing components in the experimental fusion reactor, ITER and the demonstration fusion reactor, DEMO. It has been chosen due to its high melting point, low sputtering yield and resistance to oxidation. However, there are still some issues that need addressing, such as its response to 14 MeV neutrons and helium production, products of the deuterium-tritium reaction that will be used to harness fusion energy. Additionally, the high temperatures of operation are another factor to consider. There is no dedicated materials testing device that can concurrently recreate all the conditions expected in ITER or DEMO. Previous work has focussed on the use of ion beams and linear plasma devices to try and mimic the damage induced from the neutrons and helium. Following from this work, this thesis has focused on three methods in simulating the neutron and helium damage. The three methods used in this project are; helium plasma exposures at fusion relevant temperatures to tungsten and tungsten-rhenium alloys, where rhenium was used to mimic the transmutation induced by neutrons; heavy ion (tungsten and rhenium ions) irradiations in tungsten at 400 Â°C; and proton irradiations in tungsten at 400 Â°C and 800 Â°C. Analysis of the microstructural and micromechanical properties of the exposed samples has been carried out. The effect of rhenium on the formation of a nanostructure (fuzz) in tungsten induced by helium plasma exposures was studied. Rhenium was shown to generally inhibit fuzz formation. Mechanisms by which inhibition could occur were discussed. The most recent literature had suggested that an incubation fluence was required before fuzz growth could occur, but the research in this thesis pointed more towards an alternative incubation time theory. The simultaneous effects of transmutation and displacement cascade damage induced by neutrons were mimicked via irradiations with rhenium ions into tungsten, which were compared to tungsten ion irradiations. The effect on mechanical properties of tungsten was tested using nanoindentation. Up to levels of 40 dpa and 1600 appm, at temperatures of 400 Â°C, the difference in hardness increase between the two types of irradiations was negligible. Proton irradiations at 400 Â°C and 800 Â°C, up to levels of ~2 dpa in the first 2 Âµm of the samples were explored. The hardness increase observed at 400 Â°C was much greater than that seen in the heavy ion irradiations, most likely due to the larger volume of irradiated material and the large Bragg peak in the proton irradiated samples. In both the heavy ion and proton irradiated material, higher hardness increases were observed in annealed material, in comparison to an as-received material. Impurity concentrations were observed to be an important issue when carrying out irradiation experiments, particularly at raised temperatures. Advisors/Committee Members: Mummery, Paul.

Subjects/Keywords: Nuclear Fusion; Irradiation; Tungsten; Damage

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Khan, A. (2017). ANALYSIS AND EFFECTS OF FUSION RELEVANT DAMAGE IN TUNGSTEN. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:309815

Chicago Manual of Style (16^th Edition):

Khan, Aneeqa. “ANALYSIS AND EFFECTS OF FUSION RELEVANT DAMAGE IN TUNGSTEN.” 2017. Doctoral Dissertation, University of Manchester. Accessed April 11, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:309815.

MLA Handbook (7^th Edition):

Khan, Aneeqa. “ANALYSIS AND EFFECTS OF FUSION RELEVANT DAMAGE IN TUNGSTEN.” 2017. Web. 11 Apr 2021.

Vancouver:

Khan A. ANALYSIS AND EFFECTS OF FUSION RELEVANT DAMAGE IN TUNGSTEN. [Internet] [Doctoral dissertation]. University of Manchester; 2017. [cited 2021 Apr 11]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:309815.

Council of Science Editors:

Khan A. ANALYSIS AND EFFECTS OF FUSION RELEVANT DAMAGE IN TUNGSTEN. [Doctoral Dissertation]. University of Manchester; 2017. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:309815

Loughborough University

3. Riddle, Nicholas. Impact properties of reduced-activation 9 wt. % Cr steels for nuclear fusion applications.

Degree: PhD, 2015, Loughborough University

URL: http://hdl.handle.net/2134/19589

► Materials are currently being developed for use in the International Thermonuclear Experimental Reactor, ITER; a nuclear fusion device with the aim of demonstrating the technological… (more)

Subjects/Keywords: Steel; Nuclear fusion; Fracture; Impact

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Riddle, N. (2015). Impact properties of reduced-activation 9 wt. % Cr steels for nuclear fusion applications. (Doctoral Dissertation). Loughborough University. Retrieved from http://hdl.handle.net/2134/19589

Chicago Manual of Style (16^th Edition):

Riddle, Nicholas. “Impact properties of reduced-activation 9 wt. % Cr steels for nuclear fusion applications.” 2015. Doctoral Dissertation, Loughborough University. Accessed April 11, 2021. http://hdl.handle.net/2134/19589.

MLA Handbook (7^th Edition):

Riddle, Nicholas. “Impact properties of reduced-activation 9 wt. % Cr steels for nuclear fusion applications.” 2015. Web. 11 Apr 2021.

Vancouver:

Riddle N. Impact properties of reduced-activation 9 wt. % Cr steels for nuclear fusion applications. [Internet] [Doctoral dissertation]. Loughborough University; 2015. [cited 2021 Apr 11]. Available from: http://hdl.handle.net/2134/19589.

Council of Science Editors:

Riddle N. Impact properties of reduced-activation 9 wt. % Cr steels for nuclear fusion applications. [Doctoral Dissertation]. Loughborough University; 2015. Available from: http://hdl.handle.net/2134/19589

University of Manchester

4. Khan, Aneeqa. Analysis and effects of fusion relevant damage in tungsten.

Degree: PhD, 2017, University of Manchester

URL: https://www.research.manchester.ac.uk/portal/en/theses/analysis-and-effects-of-fusion-relevant-damage-in-tungsten(49cffa39-b342-457f-9ba5-7540886c3717).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.822978

► Tungsten is a candidate material for plasma facing components in the experimental fusion reactor, ITER and the demonstration fusion reactor, DEMO. It has been chosen… (more)

▼ Tungsten is a candidate material for plasma facing components in the experimental fusion reactor, ITER and the demonstration fusion reactor, DEMO. It has been chosen due to its high melting point, low sputtering yield and resistance to oxidation. However, there are still some issues that need addressing, such as its response to 14 MeV neutrons and helium production, products of the deuterium-tritium reaction that will be used to harness fusion energy. Additionally, the high temperatures of operation are another factor to consider. There is no dedicated materials testing device that can concurrently recreate all the conditions expected in ITER or DEMO. Previous work has focussed on the use of ion beams and linear plasma devices to try and mimic the damage induced from the neutrons and helium. Following from this work, this thesis has focused on three methods in simulating the neutron and helium damage. The three methods used in this project are; helium plasma exposures at fusion relevant temperatures to tungsten and tungsten-rhenium alloys, where rhenium was used to mimic the transmutation induced by neutrons; heavy ion (tungsten and rhenium ions) irradiations in tungsten at 400 °C; and proton irradiations in tungsten at 400 °C and 800 °C. Analysis of the microstructural and micromechanical properties of the exposed samples has been carried out. The effect of rhenium on the formation of a nanostructure (fuzz) in tungsten induced by helium plasma exposures was studied. Rhenium was shown to generally inhibit fuzz formation. Mechanisms by which inhibition could occur were discussed. The most recent literature had suggested that an incubation fluence was required before fuzz growth could occur, but the research in this thesis pointed more towards an alternative incubation time theory. The simultaneous effects of transmutation and displacement cascade damage induced by neutrons were mimicked via irradiations with rhenium ions into tungsten, which were compared to tungsten ion irradiations. The effect on mechanical properties of tungsten was tested using nanoindentation. Up to levels of 40 dpa and 1600 appm, at temperatures of 400 °C, the difference in hardness increase between the two types of irradiations was negligible. Proton irradiations at 400 °C and 800 °C, up to levels of ~2 dpa in the first 2 μm of the samples were explored. The hardness increase observed at 400 °C was much greater than that seen in the heavy ion irradiations, most likely due to the larger volume of irradiated material and the large Bragg peak in the proton irradiated samples. In both the heavy ion and proton irradiated material, higher hardness increases were observed in annealed material, in comparison to an as-received material. Impurity concentrations were observed to be an important issue when carrying out irradiation experiments, particularly at raised temperatures.

Subjects/Keywords: Nuclear Fusion; Irradiation; Tungsten; Damage

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Khan, A. (2017). Analysis and effects of fusion relevant damage in tungsten. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/analysis-and-effects-of-fusion-relevant-damage-in-tungsten(49cffa39-b342-457f-9ba5-7540886c3717).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.822978

Chicago Manual of Style (16^th Edition):

Khan, Aneeqa. “Analysis and effects of fusion relevant damage in tungsten.” 2017. Doctoral Dissertation, University of Manchester. Accessed April 11, 2021. https://www.research.manchester.ac.uk/portal/en/theses/analysis-and-effects-of-fusion-relevant-damage-in-tungsten(49cffa39-b342-457f-9ba5-7540886c3717).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.822978.

MLA Handbook (7^th Edition):

Khan, Aneeqa. “Analysis and effects of fusion relevant damage in tungsten.” 2017. Web. 11 Apr 2021.

Vancouver:

Khan A. Analysis and effects of fusion relevant damage in tungsten. [Internet] [Doctoral dissertation]. University of Manchester; 2017. [cited 2021 Apr 11]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/analysis-and-effects-of-fusion-relevant-damage-in-tungsten(49cffa39-b342-457f-9ba5-7540886c3717).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.822978.

Council of Science Editors:

Khan A. Analysis and effects of fusion relevant damage in tungsten. [Doctoral Dissertation]. University of Manchester; 2017. Available from: https://www.research.manchester.ac.uk/portal/en/theses/analysis-and-effects-of-fusion-relevant-damage-in-tungsten(49cffa39-b342-457f-9ba5-7540886c3717).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.822978

Oregon State University

5. Naik, Radhika. Studying fusion reactions for effect of PCN on heavy nucleus formation and for nuclear structure effects.

Degree: PhD, Chemistry, 2007, Oregon State University

URL: http://hdl.handle.net/1957/6707

► The fusion reaction ²⁰⁸Pb (⁵⁰Ti, xn) ²⁵⁸⁻ x Rf (x = 1-3) was studied to determine PCN (probability that the mononucleus system evolves to form… (more)

▼ The fusion reaction ²⁰⁸Pb (⁵⁰Ti, xn) ²⁵⁸⁻ x Rf (x = 1-3) was studied to determine PCN (probability that the mononucleus system evolves to form a compound nucleus inside the fission saddle point) and to establish the value of Wsur (survival probability) for the given reaction experimentally. The fission excitation function was measured at five beam energies. Angular distributions were fit using the Back et al. prescription to determine JCN and σCN. The total fission cross section (σfis) and compound nucleus cross section (σCN) at each of the energies were used for calculating PCN. These experimentally determined values of PCN and σfis and the values of σEVR determined in previous studies of this system were used in the equation σEVR = σc x PCN × Wsur to arrive at Wsur for each of the energies. The experimental value of Wsur for 1n channel agrees very well with the one based on theoretical predictions of Möller et al. The subsequent lowering in Wsur with beam energy is attributed to onset of 2n and 3n evaporation channels. The fusion reaction ⁹Li+ ⁷⁰Zn was studied to determine the effects of nuclear structure of the projectile (neutron skin) on fusion. The fusion excitation function was measured at seven near- and sub-barrier beam energies. Radioactivity in the irradiated target was measured by γ-spectroscopy and in radiochemically separated EVRs by β-spectroscopy. The ⁹Li fusion radius determined by fitting the excitation function with Wong formula was 12.1 ± 1.0fm, much larger than 2.5fm given by R₀xA¹/³. This extension of the radius is attributed to the presence of spatially extended neutron skin. The excitation function also showed a large sub-barrier fusion enhancement not explained by standard coupled channel model. An attempt was made at measuring the fusion excitation function with ¹¹Li projectile (neutron halo nucleus) which would enable us to do a comparative study as ⁹Li is the core of ¹¹Li halo nucleus but it failed due to low beam intensity. Advisors/Committee Members: Loveland, Walter D. (advisor), Watson, Philip (committee member).

Subjects/Keywords: nuclear; Nuclear fusion

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Naik, R. (2007). Studying fusion reactions for effect of PCN on heavy nucleus formation and for nuclear structure effects. (Doctoral Dissertation). Oregon State University. Retrieved from http://hdl.handle.net/1957/6707

Chicago Manual of Style (16^th Edition):

Naik, Radhika. “Studying fusion reactions for effect of PCN on heavy nucleus formation and for nuclear structure effects.” 2007. Doctoral Dissertation, Oregon State University. Accessed April 11, 2021. http://hdl.handle.net/1957/6707.

MLA Handbook (7^th Edition):

Naik, Radhika. “Studying fusion reactions for effect of PCN on heavy nucleus formation and for nuclear structure effects.” 2007. Web. 11 Apr 2021.

Vancouver:

Naik R. Studying fusion reactions for effect of PCN on heavy nucleus formation and for nuclear structure effects. [Internet] [Doctoral dissertation]. Oregon State University; 2007. [cited 2021 Apr 11]. Available from: http://hdl.handle.net/1957/6707.

Council of Science Editors:

Naik R. Studying fusion reactions for effect of PCN on heavy nucleus formation and for nuclear structure effects. [Doctoral Dissertation]. Oregon State University; 2007. Available from: http://hdl.handle.net/1957/6707

University of Sydney

6. Poznic, Dominic. Statistical and Information Analysis of Plasma Diagnostics .

Degree: 2019, University of Sydney

URL: http://hdl.handle.net/2123/20189

► Model comparison using Bayesian evidence, an analysis technique not previously used in plasma physics, is demonstrated on data from two experimental fusion devices. In the… (more)

Subjects/Keywords: Bayesian statistics; nuclear fusion; nuclear fusion; experimental design; Polywell; MAST

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Poznic, D. (2019). Statistical and Information Analysis of Plasma Diagnostics . (Thesis). University of Sydney. Retrieved from http://hdl.handle.net/2123/20189

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Poznic, Dominic. “Statistical and Information Analysis of Plasma Diagnostics .” 2019. Thesis, University of Sydney. Accessed April 11, 2021. http://hdl.handle.net/2123/20189.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Poznic, Dominic. “Statistical and Information Analysis of Plasma Diagnostics .” 2019. Web. 11 Apr 2021.

Vancouver:

Poznic D. Statistical and Information Analysis of Plasma Diagnostics . [Internet] [Thesis]. University of Sydney; 2019. [cited 2021 Apr 11]. Available from: http://hdl.handle.net/2123/20189.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Poznic D. Statistical and Information Analysis of Plasma Diagnostics . [Thesis]. University of Sydney; 2019. Available from: http://hdl.handle.net/2123/20189

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

7. Edilson Crema. Estudo da fusão nuclear de 14N com 27Al, 28Si e 29Si.

Degree: 1983, University of São Paulo

URL: http://www.teses.usp.br/teses/disponiveis/43/43131/tde-21022014-145443/

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Foram medidas as funções de excitação de fusão de 14N+ 27Al, 14N + 28Si e 14N + 29Si por detecção dos resíduos de evaporação com… (more)

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Foram medidas as funções de excitação de fusão de 14N+ 27Al, 14N + 28Si e 14N + 29Si por detecção dos resíduos de evaporação com um telescópio proporcional E-E. Com o objetivo de determinar se a origem da limitação da seção de choque total de fusão em energias intermediárias era devido a propriedades do núcleo composto ou do canal de entrada os resultados experimentais foram interpretados do ponto de vista do: modelo de Horn-Ferguson, modelo de Lozano-Madurga, modelo de Glas-Mosel, modelo da linha de yrast, modelo da linha estatística de yrast, modelo da superposição de níveis, modelo das etapas intermediárias. Foi feita uma discussão da origem destes modelos e um estudo comparativo dos valores que seus parâmetros assumem numa larga faixa de massa inclusive os calculados neste trabalho. Para estes concluímos que existem indicações de que o canal de entrada pode ter influência na limitação da seção de choque de fusão, mas que é necessário medir as reações periféricas nos três sistemas para assegurar esta hipótese.

Fusion excitation functions were measured for the systems 14N + 27Al, 14N + 28Si and 14N + 29Si by detecting the evaporation residues with a E-E proportional telescope. Since the principal objective of this work was to determine the roles which the formation of the compound nucleus and the specific properties of entrance channel play in the observed limitations of the total fusion cross section, the experimental results were analyzed in the light of the following models: Horn-Ferguson, Lozano-Madurga, Glas-Mosel, Yrast Line, Statistical Yrast Line, Superposition of Levels, Intermediate Step. The results of these theoretical analyses indicate that the entrance channel exerts some influence on the fusion cross section, but to secure this conclusion it is suggested that measurements on direct reaction mechanisms for these systems be made.

Advisors/Committee Members: Juan Carlos Acquadro Quacchia, Paul Qualifik, Oscar Sala.

Subjects/Keywords: Nuclear fusion; Nuclear fusion

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Crema, E. (1983). Estudo da fusão nuclear de 14N com 27Al, 28Si e 29Si. (Doctoral Dissertation). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/43/43131/tde-21022014-145443/

Chicago Manual of Style (16^th Edition):

Crema, Edilson. “Estudo da fusão nuclear de 14N com 27Al, 28Si e 29Si.” 1983. Doctoral Dissertation, University of São Paulo. Accessed April 11, 2021. http://www.teses.usp.br/teses/disponiveis/43/43131/tde-21022014-145443/.

MLA Handbook (7^th Edition):

Crema, Edilson. “Estudo da fusão nuclear de 14N com 27Al, 28Si e 29Si.” 1983. Web. 11 Apr 2021.

Vancouver:

Crema E. Estudo da fusão nuclear de 14N com 27Al, 28Si e 29Si. [Internet] [Doctoral dissertation]. University of São Paulo; 1983. [cited 2021 Apr 11]. Available from: http://www.teses.usp.br/teses/disponiveis/43/43131/tde-21022014-145443/.

Council of Science Editors:

Crema E. Estudo da fusão nuclear de 14N com 27Al, 28Si e 29Si. [Doctoral Dissertation]. University of São Paulo; 1983. Available from: http://www.teses.usp.br/teses/disponiveis/43/43131/tde-21022014-145443/

University of Manchester

8. Fan, Ying. Serial verb constructions in Mandarin Chinese and Jinjiang Southern Min.

Degree: PhD, 2016, University of Manchester

URL: https://www.research.manchester.ac.uk/portal/en/theses/serial-verb-constructions-in-mandarin-chinese-and-jinjiang-southern-min(965bd89d-af9a-446a-9cbe-19d90a0d9344).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.686798

► This study identifies two syntactically distinguishable types of Serial Verb Constructions (SVCs) in Mandarin Chinese (MC) and Jinjiang Southern Min (JSM), corresponding to the nuclear… (more)

▼ This study identifies two syntactically distinguishable types of Serial Verb Constructions (SVCs) in Mandarin Chinese (MC) and Jinjiang Southern Min (JSM), corresponding to the nuclear and core distinction made in Role and Reference Grammar (Foley and Van Valin 1984, Foley and Olson 1985, Van Valin and LaPolla 1997). This distinction is also made on the basis of a general consensus of the cross-linguistic classifications of the processes of monoclausal multi-verb construction formation (e.g., Butt 1993, 1997, Baker and Harvey 2010): namely, predicate fusion and argument fusion. In this study, I propose two sets of diagnostics to establish the distinction; these go beyond the range covered in previous studies (e.g., Olson 1981, Foley and Olson 1985, Crowley 2002, Chang 2007). In the first set of diagnostics in this study, seven inter-clausal diagnostics are considered as the threshold where the behaviours of bi-clausal structures and SVCs split. These diagnostics include independent negation, passivisation of the object of V2, independent modification by temporal adverbial, independent marking of viewpoint aspect, independent modification by manner adverbial, prosodic structure and the Coordinate Structure Constraint (Ross 1967) that is employed in a more restricted manner. In the second set of diagnostics, four intra-clausal diagnostics are adopted to make the distinction between nuclear and core SVCs, which include passivisation of O1, insertion of intervening material, coordination within the SVC, and obligatory topicalisation of undergoer argument. Of particular interest is the possibility that the same string of verbs may occur in superficially similar, but structurally different, SVCs: for example, the Cause-Effect SVC and the Excessive SVC. The diagnostics employed in this study are proposed as a novel method to establish the distinction between the SVCs and the bi-clausal structures, and more importantly, between core and nuclear types of SVC. Contributing to the originality of the new method of diagnosing the status of the SVCs proposed in this study, I add five novel diagnostics, such as passivisation of the object of V2, independent marking of viewpoint aspect, tone sandhi between adjacent verbs, coordination within the SVC and obligatory topicalisation of the undergoer argument, in addition to those that have been employed in the literature. I restrict myself to data of MC and JSM in discussing the rationale of the diagnostics. However, this novel method of identifying SVCs is expected to be cross-linguistically applicable with consistent results, while at the same time allowing for the possibility of cross-linguistic differences in the semantic sub-types of SVCs identified in each language.

Subjects/Keywords: 495.1; Serial Verb Constructions; Nuclear; Core; Predicate Fusion; Argument Fusion

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APA (6^th Edition):

Fan, Y. (2016). Serial verb constructions in Mandarin Chinese and Jinjiang Southern Min. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/serial-verb-constructions-in-mandarin-chinese-and-jinjiang-southern-min(965bd89d-af9a-446a-9cbe-19d90a0d9344).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.686798

Chicago Manual of Style (16^th Edition):

Fan, Ying. “Serial verb constructions in Mandarin Chinese and Jinjiang Southern Min.” 2016. Doctoral Dissertation, University of Manchester. Accessed April 11, 2021. https://www.research.manchester.ac.uk/portal/en/theses/serial-verb-constructions-in-mandarin-chinese-and-jinjiang-southern-min(965bd89d-af9a-446a-9cbe-19d90a0d9344).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.686798.

MLA Handbook (7^th Edition):

Fan, Ying. “Serial verb constructions in Mandarin Chinese and Jinjiang Southern Min.” 2016. Web. 11 Apr 2021.

Vancouver:

Fan Y. Serial verb constructions in Mandarin Chinese and Jinjiang Southern Min. [Internet] [Doctoral dissertation]. University of Manchester; 2016. [cited 2021 Apr 11]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/serial-verb-constructions-in-mandarin-chinese-and-jinjiang-southern-min(965bd89d-af9a-446a-9cbe-19d90a0d9344).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.686798.

Council of Science Editors:

Fan Y. Serial verb constructions in Mandarin Chinese and Jinjiang Southern Min. [Doctoral Dissertation]. University of Manchester; 2016. Available from: https://www.research.manchester.ac.uk/portal/en/theses/serial-verb-constructions-in-mandarin-chinese-and-jinjiang-southern-min(965bd89d-af9a-446a-9cbe-19d90a0d9344).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.686798

University of Manchester

9. Menzies, Luke. Modelling Helium Embrittlement in Iron Based Metals Under DEMO Conditions.

Degree: 2018, University of Manchester

URL: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:314784

► Steel components within fusion reactors will be subject to high transmutation rates due to high energy neutrons. In iron based alloys such as steels, high… (more)

▼ Steel components within fusion reactors will be subject to high transmutation rates due to high energy neutrons. In iron based alloys such as steels, high amounts of helium accumulate through transmutation. This leads to helium embrittlement through helium accumulating on the grain boundaries of metal. Worst case scenario predictions were made for DEMO, estimating that for a grain size of 5 micro-meters, embrittlement could happen within 2 years of the blanket region of DEMO. This thesis elaborates on previous worst case scenario calculations by including inter-granular tapping mechanisms, within rate theory simulations. A rate theory code was developed for the purpose of this work, tailored towards a fusion environment. Calculations were performed using rate theory that predicted the timescales in which helium embrittlement occurred within a conceptual DEMO design in the first wall region and the blanket region. The calculations used several parameter sets, where preliminary simulations were performed using the parameter sets, that were compared with cluster density data determined using Transmission Electron Microscopy (TEM) and Positron Annihilation Spectroscopy (PAS). The simulations showed that the helium embrittlement time was heavily influenced by the chosen dislocation density, parameter set and grain size. The simulations conducted to represent the blanket region, showed an increase as high as 94% from the 2 years that has previously been predicted under certain scenarios. However results also showed that assuming a certain parameter set with a low dislocation density, showed no significant increase in embrittlement time. This was not a concern since it was concluded that advanced steel concepts would be expected to have a small average grain size, that would dramatically increase the embrittlement time. The work in this thesis also focused on defect interaction with dislocations. A model was constructed that made use of elasticity theory and VASP calculations that produced the interaction energy map for various defects with an edge dislocation. The interaction energy map for helium interstitials with an edge dislocation was compared with molecular dynamics (MD) simulations produced for this work. The model and simulations showed good agreement. Temperature effects were then included in the model that allowed the concentration around a dislocation to be temperature dependent. These temperature dependent interaction energy maps were then implemented into the advection-diffusion equation, that were solved numerically to explore the capture efficiencies and bias towards certain defects within iron. These values were then used within the rate theory simulations to produce temperature effects on the dislocation sink strengths for vacancies, SIA and helium interstitials. Advisors/Committee Members: JIMENEZ-MELERO, ENRIQUE E, RACE, CHRISTOPHER C, Mummery, Paul, Jimenez-Melero, Enrique, Race, Christopher.

Subjects/Keywords: Nuclear Fusion; Materials Modelling; Rate Theory; Dislocations

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APA (6^th Edition):

Menzies, L. (2018). Modelling Helium Embrittlement in Iron Based Metals Under DEMO Conditions. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:314784

Chicago Manual of Style (16^th Edition):

Menzies, Luke. “Modelling Helium Embrittlement in Iron Based Metals Under DEMO Conditions.” 2018. Doctoral Dissertation, University of Manchester. Accessed April 11, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:314784.

MLA Handbook (7^th Edition):

Menzies, Luke. “Modelling Helium Embrittlement in Iron Based Metals Under DEMO Conditions.” 2018. Web. 11 Apr 2021.

Vancouver:

Menzies L. Modelling Helium Embrittlement in Iron Based Metals Under DEMO Conditions. [Internet] [Doctoral dissertation]. University of Manchester; 2018. [cited 2021 Apr 11]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:314784.

Council of Science Editors:

Menzies L. Modelling Helium Embrittlement in Iron Based Metals Under DEMO Conditions. [Doctoral Dissertation]. University of Manchester; 2018. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:314784

University of Oxford

10. Leide, Alexander. Reaction-bonded silicon carbide for nuclear fusion blanket applications.

Degree: PhD, 2020, University of Oxford

URL: http://ora.ox.ac.uk/objects/uuid:b1a0f22a-b59e-4eee-a623-da4ed8cbb18a ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.808316

► Reaction-bonded silicon carbide has properties which make it useful for certain components of a nuclear fusion reactor, but its response to irradiation has not been… (more)

Subjects/Keywords: Nuclear fusion; Radiation damage; Materials science

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APA (6^th Edition):

Leide, A. (2020). Reaction-bonded silicon carbide for nuclear fusion blanket applications. (Doctoral Dissertation). University of Oxford. Retrieved from http://ora.ox.ac.uk/objects/uuid:b1a0f22a-b59e-4eee-a623-da4ed8cbb18a ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.808316

Chicago Manual of Style (16^th Edition):

Leide, Alexander. “Reaction-bonded silicon carbide for nuclear fusion blanket applications.” 2020. Doctoral Dissertation, University of Oxford. Accessed April 11, 2021. http://ora.ox.ac.uk/objects/uuid:b1a0f22a-b59e-4eee-a623-da4ed8cbb18a ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.808316.

MLA Handbook (7^th Edition):

Leide, Alexander. “Reaction-bonded silicon carbide for nuclear fusion blanket applications.” 2020. Web. 11 Apr 2021.

Vancouver:

Leide A. Reaction-bonded silicon carbide for nuclear fusion blanket applications. [Internet] [Doctoral dissertation]. University of Oxford; 2020. [cited 2021 Apr 11]. Available from: http://ora.ox.ac.uk/objects/uuid:b1a0f22a-b59e-4eee-a623-da4ed8cbb18a ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.808316.

Council of Science Editors:

Leide A. Reaction-bonded silicon carbide for nuclear fusion blanket applications. [Doctoral Dissertation]. University of Oxford; 2020. Available from: http://ora.ox.ac.uk/objects/uuid:b1a0f22a-b59e-4eee-a623-da4ed8cbb18a ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.808316

University of Newcastle

11. Barnes, Michael. The ³He(d,p)He⁴ nuclear fusion reaction as a source of mega-voltage protons for the production of fluorine-18 for PET applications.

Degree: Physics, 2009, University of Newcastle

URL: http://hdl.handle.net/1959.13/38557

►

Masters Research - Master of Philosophy (Physics)

Fluoro-deoxyglucose (FDG) labeled with fluorine-18 is commonly used in positron emission tomography (PET) imaging. PET imaging is a… (more)

▼

Masters Research - Master of Philosophy (Physics)

Fluoro-deoxyglucose (FDG) labeled with fluorine-18 is commonly used in positron emission tomography (PET) imaging. PET imaging is a powerful tool used primarily in the diagnosis and management of cancer. The growth of PET has been limited partly by the difficulties associated in producing fluorine-18. This project involves a theoretical investigation of a novel method of producing fluorine-18 utilising proton generation via the ³He(d,p)⁴He nuclear reaction. Currently the most common method of producing fluorine-18 for PET is with a medical cyclotron that accelerates protons to mega-voltage energies. These protons are then directed onto a target rich in oxygen-18. This initiates the ¹⁸O(p,n)¹⁸F reaction to produce fluorine-18. The ³He(d,p)⁴He reaction, utilized for the present study, has a Q-value of 18.35 MeV and this results in protons being produced at energies similar to that produced in a medical cyclotron. This reaction was investigated as an alternative proton source for the ¹⁸O(p,n)¹⁸F reaction. The expected advantage of this method over the cyclotron is that particles need only be accelerated to keV energies rather than the tens of MeV that a medical cyclotron accelerates protons to. This is expected to significantly reduce the cost and associated size of the system. Two systems based on the ³He(d,p)⁴He reaction were designed and calculations were performed to determine the respective yields of fluorine-18. The first system involved separate targets for the ³He(d,p)⁴He and ¹⁸O(p,n)¹⁸F reactions. Helium-3 ions are initially fired onto a deuterated plastic target. A heavy-water (H₂O¹⁸) target is placed immediately behind this plastic target to absorb mega-voltage protons produced by the reaction ³He(d,p)⁴He in the plastic. The second system involved a single, super heavy water (D₂O¹⁸) target onto which helium-3 is fired so that both the ³He(d,p)⁴He and ¹⁸O(p,n)¹⁸F reactions can occur concurrently in the one target. The input parameters of energy and beam current for the helium-3 beam required for the ³He(d,p)⁴He reaction were selected on the basis of the performance of currently available ion sources and in particular the saddle-field ion source. Practical considerations such as radiation safety, target degradation and lifetime and ultra high vacuum (UHV) issues were also investigated to further determine the feasibility of the two systems. With the beam current and energy at the extreme limits of the saddle-field ion source it was calculated that insufficient fluorine-18 could be produced daily to supply a PET facility with FDG. It was also found that the high helium-3 beam currents and energy required to produce significant amounts of fluorine-18 resulted in prohibitive temperature rises in the targets that would likely result in target vaporization..

Advisors/Committee Members: University of Newcastle. Faculty of Science and Information Technology, School of Mathematics and Physical Sciences.

Subjects/Keywords: positron emission tomography; nuclear fusion; fluoro deoxyglucose

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APA (6^th Edition):

Barnes, M. (2009). The ³He(d,p)He⁴ nuclear fusion reaction as a source of mega-voltage protons for the production of fluorine-18 for PET applications. (Masters Thesis). University of Newcastle. Retrieved from http://hdl.handle.net/1959.13/38557

Chicago Manual of Style (16^th Edition):

Barnes, Michael. “The ³He(d,p)He⁴ nuclear fusion reaction as a source of mega-voltage protons for the production of fluorine-18 for PET applications.” 2009. Masters Thesis, University of Newcastle. Accessed April 11, 2021. http://hdl.handle.net/1959.13/38557.

MLA Handbook (7^th Edition):

Barnes, Michael. “The ³He(d,p)He⁴ nuclear fusion reaction as a source of mega-voltage protons for the production of fluorine-18 for PET applications.” 2009. Web. 11 Apr 2021.

Vancouver:

Barnes M. The ³He(d,p)He⁴ nuclear fusion reaction as a source of mega-voltage protons for the production of fluorine-18 for PET applications. [Internet] [Masters thesis]. University of Newcastle; 2009. [cited 2021 Apr 11]. Available from: http://hdl.handle.net/1959.13/38557.

Council of Science Editors:

Barnes M. The ³He(d,p)He⁴ nuclear fusion reaction as a source of mega-voltage protons for the production of fluorine-18 for PET applications. [Masters Thesis]. University of Newcastle; 2009. Available from: http://hdl.handle.net/1959.13/38557

Texas Tech University

12. Kwon, Myeung Hoi. Muon catalyzed fusion process.

Degree: Physics, 1987, Texas Tech University

URL: http://hdl.handle.net/2346/20149

Subjects/Keywords: Muons; Nuclear fusion

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APA (6^th Edition):

Kwon, M. H. (1987). Muon catalyzed fusion process. (Thesis). Texas Tech University. Retrieved from http://hdl.handle.net/2346/20149

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Kwon, Myeung Hoi. “Muon catalyzed fusion process.” 1987. Thesis, Texas Tech University. Accessed April 11, 2021. http://hdl.handle.net/2346/20149.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Kwon, Myeung Hoi. “Muon catalyzed fusion process.” 1987. Web. 11 Apr 2021.

Vancouver:

Kwon MH. Muon catalyzed fusion process. [Internet] [Thesis]. Texas Tech University; 1987. [cited 2021 Apr 11]. Available from: http://hdl.handle.net/2346/20149.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Kwon MH. Muon catalyzed fusion process. [Thesis]. Texas Tech University; 1987. Available from: http://hdl.handle.net/2346/20149

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of Pretoria

13. [No author]. Purifying coal for the production of nuclear graphite .

Degree: 2008, University of Pretoria

URL: http://upetd.up.ac.za/thesis/available/etd-04212008-124149/

► Carbon materials play a fundamental role in the development of fusion reactors, for both the generation of electric power and the production of nuclear materials.… (more)

▼ Carbon materials play a fundamental role in the development of fusion reactors, for both the generation of electric power and the production of nuclear materials. It is possible to synthesise graphite and carbon materials from coal. Coal is available in large quantities and could be used for the production of high-purity carbon graphite. However, it contains large quantities of impurities that need to be removed prior to graphitisation/carbonisation. The impurity levels of certain elements in this graphite must be kept at very low levels. Boron, which absorbs neutrons strongly, should be below 500 ppb. Europium and gadolinium, which absorb neutrons and are activated to highly radioactive products, as is cobalt, should be as low as 50 ppb. Lithium transforms to tritium, which leads to the circulating helium becoming radioactive. Other elements, such as calcium, sodium, silicon, thorium and uranium, should not be ignored. The purpose of this study was to lower or remove completely the impurities and trace elements in coal that affect the quality of nuclear-grade graphite. The organic part of Tshikondeni coal was dissolved in a solvent, dimethylformamide (DMF), on addition of sodium hydroxide. The first stage of purification is centrifugation and filtration, which removes most of the impurities. The recovered organic material, known as ‘Refcoal’, may be converted to graphitisable coke. Some elements, significantly boron and cobalt, associate with the organic material in solution and are not sufficiently separated by centrifugation and filtration. Further purification was employed during each process step in the conversion of coal solution into graphite. Different methods of purification were employed in this study. They included chlorination, acid treatment and the ion-exchange or complexation method. Chlorine gas and hexachlorocyclohexane (benzene hexachloride) were used in the chlorination method. Acids such as hydrochloric, hydrofluoric and ascorbic were used in acid treatment. In the ion-exchange method, reagents such as methane, starch, potassium cyanide, ethylene-diaminetetraacetic acid, sodium fluoride, sodium sulphate, ice, glycerol and sodium nitrate were used. All the treated Refcoal was coked at 1 000º C. Pyrolysis was applied in other methods with the aim of volatilising elements that form volatile halides at higher temperatures. Analysis was done for elements such as calcium, cobalt, europium, gadolinium, lithium, sodium, silicon, thorium and uranium, and other elements in the periodic table. Inductively coupled plasma mass spectroscopy and inductively coupled plasma optical emission spectroscopy were used to analyse the concentrations of the trace elements in the coal (treated and untreated) and the coked Refcoal. In inductively coupled plasma mass spectroscopy, microwave digestion and fusion were applied as methods of preparation. However, the instrumentation gave different results for the same sample. The results showed that specific methods work for specific elements. The chlorination method and the… Advisors/Committee Members: Dr D L Morgan (advisor).

Subjects/Keywords: Purification; Nuclear graphite; Fusion reactors; Nuclear materials; UCTD

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APA (6^th Edition):

author], [. (2008). Purifying coal for the production of nuclear graphite . (Masters Thesis). University of Pretoria. Retrieved from http://upetd.up.ac.za/thesis/available/etd-04212008-124149/

Chicago Manual of Style (16^th Edition):

author], [No. “Purifying coal for the production of nuclear graphite .” 2008. Masters Thesis, University of Pretoria. Accessed April 11, 2021. http://upetd.up.ac.za/thesis/available/etd-04212008-124149/.

MLA Handbook (7^th Edition):

author], [No. “Purifying coal for the production of nuclear graphite .” 2008. Web. 11 Apr 2021.

Vancouver:

author] [. Purifying coal for the production of nuclear graphite . [Internet] [Masters thesis]. University of Pretoria; 2008. [cited 2021 Apr 11]. Available from: http://upetd.up.ac.za/thesis/available/etd-04212008-124149/.

Council of Science Editors:

author] [. Purifying coal for the production of nuclear graphite . [Masters Thesis]. University of Pretoria; 2008. Available from: http://upetd.up.ac.za/thesis/available/etd-04212008-124149/

University of California – Berkeley

14. Kramer, Kevin James. Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System.

Degree: Nuclear Engineering, 2010, University of California – Berkeley

URL: http://www.escholarship.org/uc/item/9204g3s4

► This study investigates the neutronics design aspects of a hybrid fusion-fission energy system called the Laser Fusion-Fission Hybrid (LFFH). A LFFH combines current Laser Inertial… (more)

▼ This study investigates the neutronics design aspects of a hybrid fusion-fission energy system called the Laser Fusion-Fission Hybrid (LFFH). A LFFH combines current Laser Inertial Confinement fusion technology with that of advanced fission reactor technology to produce a system that eliminates many of the negative aspects of pure fusion or pure fission systems. When examining the LFFH energy mission, a significant portion of the United States and world energy production could be supplied by LFFH plants. The LFFH engine described utilizes a central fusion chamber surrounded by multiple layers of multiplying and moderating media. These layers, or blankets, include coolant plenums, a beryllium (Be) multiplier layer, a fertile fission blanket and a graphite-pebble reflector. Each layer is separated by perforated oxide dispersion strengthened (ODS) ferritic steel walls. The central fusion chamber is surrounded by an ODS ferritic steel first wall. The first wall is coated with 250-500 μm of tungsten to mitigate x-ray damage. The first wall is cooled by Li₁₇Pb₈₃ eutectic, chosen for its neutron multiplication and good heat transfer properties. The Li₁₇Pb₈₃ flows in a jacket around the first wall to an extraction plenum. The main coolant injection plenum is immediately behind the Li₁₇Pb₈₃, separated from the Li₁₇Pb₈₃ by a solid ODS wall. This main system coolant is the molten salt flibe (2LiF-BeF₂), chosen for beneficial neutronics and heat transfer properties. The use of flibe enables both fusion fuel production (tritium) and neutron moderation and multiplication for the fission blanket. A Be pebble (1 cm diameter) multiplier layer surrounds the coolant injection plenum and the coolant flows radially through perforated walls across the bed. Outside the Be layer, a fission fuel layer comprised of depleted uranium contained in Tristructural-isotropic (TRISO) fuel particles having a packing fraction of 20% in 2 cm diameter fuel pebbles. The fission blanket is cooled by the same radial flibe flow that travels through perforated ODS walls to the reflector blanket. This reflector blanket is 75 cm thick comprised of 2 cm diameter graphite pebbles cooled by flibe. The flibe extraction plenum surrounds the reflector bed. Detailed neutronics designs studies are performed to arrive at the described design.The LFFH engine thermal power is controlled using a technique of adjusting the ⁶Li/⁷Li enrichment in the primary and secondary coolants. The enrichment adjusts system thermal power in the design by increasing tritium production while reducing fission. To perform the simulations and design of the LFFH engine, a new software program named LFFH Nuclear Control (LNC) was developed in C++ to extend the functionality of existing neutron transport and depletion software programs. Neutron transport calculations are performed with MCNP5. Depletion calculations are performed using Monteburns 2.0, which utilizes…

Subjects/Keywords: Engineering, Nuclear; Energy; Fission; Fusion; Hybrid; LIFE; Nuclear

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APA (6^th Edition):

Kramer, K. J. (2010). Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/9204g3s4

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Kramer, Kevin James. “Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System.” 2010. Thesis, University of California – Berkeley. Accessed April 11, 2021. http://www.escholarship.org/uc/item/9204g3s4.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Kramer, Kevin James. “Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System.” 2010. Web. 11 Apr 2021.

Vancouver:

Kramer KJ. Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System. [Internet] [Thesis]. University of California – Berkeley; 2010. [cited 2021 Apr 11]. Available from: http://www.escholarship.org/uc/item/9204g3s4.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Kramer KJ. Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System. [Thesis]. University of California – Berkeley; 2010. Available from: http://www.escholarship.org/uc/item/9204g3s4

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of California – Berkeley

15. Seifried, Jeffrey Edwin. Adjoint-Based Uncertainty Quantification with MCNP.

Degree: Nuclear Engineering, 2011, University of California – Berkeley

URL: http://www.escholarship.org/uc/item/4xs3p115

► This work serves to quantify the instantaneous uncertainties in neutron transport simulations born from nuclear data and statistical counting uncertainties. Perturbation and adjoint theories are… (more)

Subjects/Keywords: Nuclear engineering; adjoint; energy; hybrid fission fusion; nuclear; sensitivity; uncertainty quantification

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APA (6^th Edition):

Seifried, J. E. (2011). Adjoint-Based Uncertainty Quantification with MCNP. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/4xs3p115

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Seifried, Jeffrey Edwin. “Adjoint-Based Uncertainty Quantification with MCNP.” 2011. Thesis, University of California – Berkeley. Accessed April 11, 2021. http://www.escholarship.org/uc/item/4xs3p115.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Seifried, Jeffrey Edwin. “Adjoint-Based Uncertainty Quantification with MCNP.” 2011. Web. 11 Apr 2021.

Vancouver:

Seifried JE. Adjoint-Based Uncertainty Quantification with MCNP. [Internet] [Thesis]. University of California – Berkeley; 2011. [cited 2021 Apr 11]. Available from: http://www.escholarship.org/uc/item/4xs3p115.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Seifried JE. Adjoint-Based Uncertainty Quantification with MCNP. [Thesis]. University of California – Berkeley; 2011. Available from: http://www.escholarship.org/uc/item/4xs3p115

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of California – Berkeley

16. Powers, Jeffrey. TRISO Fuel Performance: Modeling, Integration into Mainstream Design Studies, and Application to a Thorium-fueled Fusion-Fission Hybrid Blanket.

Degree: Nuclear Engineering, 2011, University of California – Berkeley

URL: http://www.escholarship.org/uc/item/6v84b2c6

► This study focused on creating a new tristructural isotropic (TRISO) coated particle fuel performance model and demonstrating the integration of this model into an existing… (more)

▼ This study focused on creating a new tristructural isotropic (TRISO) coated particle fuel performance model and demonstrating the integration of this model into an existing system of neutronics and heat transfer codes, creating a user-friendly option for including fuel performance analysis within system design optimization and system-level trade-off studies. The end product enables both a deeper understanding and better overall system performance of nuclear energy systems limited or greatly impacted by TRISO fuel performance. A thorium-fueled hybrid fusion-fission Laser Inertial Fusion Energy (LIFE) blanket design was used for illustrating the application of this new capability and demonstrated both the importance of integrating fuel performance calculations into mainstream design studies and the impact that this new integrated analysis had on system-level design decisions.A new TRISO fuel performance model named TRIUNE was developed and verified and validated during this work with a novel methodology established for simulating the actual lifetime of a TRISO particle during repeated passes through a pebble bed. In addition, integrated self-consistent calculations were performed for neutronics depletion analysis, heat transfer calculations, and then fuel performance modeling for a full parametric study that encompassed over 80 different design options that went through all three phases of analysis. Lastly, side studies were performed that included a comparison of thorium and depleted uranium (DU) LIFE blankets as well as some uncertainty quantification work to help guide future experimental work by assessing what material properties in TRISO fuel performance modeling are most in need of improvement.A recommended thorium-fueled hybrid LIFE engine design was identified with an initial fuel load of 20MT of thorium, 15% TRISO packing within the graphite fuel pebbles, and a 20cm neutron multiplier layer with beryllium pebbles in flibe molten salt coolant. It operated at a system power level of 2000 MW_th, took about 3.5 years to reach full plateau power, and was capable of an End of Plateau burnup of 38.7 %FIMA if considering just the neutronic constraints in the system design; however, fuel performance constraints led to a maximum credible burnup of 12.1 %FIMA due to a combination of internal gas pressure and irradiation effects on the TRISO materials (especially PyC) leading to SiC pressure vessel failures. The optimal neutron spectrum for the thorium-fueled blanket options evaluated seemed to favor a hard spectrum (low but non-zero neutron multiplier thicknesses and high TRISO packing fractions) in terms of neutronic performance but the fuel performance constraints demonstrated that a significantly softer spectrum would be needed to decrease the rate of accumulation of fast neutron fluence in order to improve the maximum credible burnup the system could achieve.

Subjects/Keywords: Nuclear engineering; Materials Science; Energy; fission; fuel; fusion; materials; nuclear; TRISO

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APA (6^th Edition):

Powers, J. (2011). TRISO Fuel Performance: Modeling, Integration into Mainstream Design Studies, and Application to a Thorium-fueled Fusion-Fission Hybrid Blanket. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/6v84b2c6

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Powers, Jeffrey. “TRISO Fuel Performance: Modeling, Integration into Mainstream Design Studies, and Application to a Thorium-fueled Fusion-Fission Hybrid Blanket.” 2011. Thesis, University of California – Berkeley. Accessed April 11, 2021. http://www.escholarship.org/uc/item/6v84b2c6.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Powers, Jeffrey. “TRISO Fuel Performance: Modeling, Integration into Mainstream Design Studies, and Application to a Thorium-fueled Fusion-Fission Hybrid Blanket.” 2011. Web. 11 Apr 2021.

Vancouver:

Powers J. TRISO Fuel Performance: Modeling, Integration into Mainstream Design Studies, and Application to a Thorium-fueled Fusion-Fission Hybrid Blanket. [Internet] [Thesis]. University of California – Berkeley; 2011. [cited 2021 Apr 11]. Available from: http://www.escholarship.org/uc/item/6v84b2c6.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Powers J. TRISO Fuel Performance: Modeling, Integration into Mainstream Design Studies, and Application to a Thorium-fueled Fusion-Fission Hybrid Blanket. [Thesis]. University of California – Berkeley; 2011. Available from: http://www.escholarship.org/uc/item/6v84b2c6

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of Pretoria

17. Phupheli, Milingoni Robert. Purifying coal for the production of nuclear graphite.

Degree: MSc, Chemistry, 2008, University of Pretoria

URL: http://hdl.handle.net/2263/24051

► Carbon materials play a fundamental role in the development of fusion reactors, for both the generation of electric power and the production of nuclear materials.… (more)

▼ Carbon materials play a fundamental role in the development of fusion reactors, for both the generation of electric power and the production of nuclear materials. It is possible to synthesise graphite and carbon materials from coal. Coal is available in large quantities and could be used for the production of high-purity carbon graphite. However, it contains large quantities of impurities that need to be removed prior to graphitisation/carbonisation. The impurity levels of certain elements in this graphite must be kept at very low levels. Boron, which absorbs neutrons strongly, should be below 500 ppb. Europium and gadolinium, which absorb neutrons and are activated to highly radioactive products, as is cobalt, should be as low as 50 ppb. Lithium transforms to tritium, which leads to the circulating helium becoming radioactive. Other elements, such as calcium, sodium, silicon, thorium and uranium, should not be ignored. The purpose of this study was to lower or remove completely the impurities and trace elements in coal that affect the quality of nuclear-grade graphite. The organic part of Tshikondeni coal was dissolved in a solvent, dimethylformamide (DMF), on addition of sodium hydroxide. The first stage of purification is centrifugation and filtration, which removes most of the impurities. The recovered organic material, known as ‘Refcoal’, may be converted to graphitisable coke. Some elements, significantly boron and cobalt, associate with the organic material in solution and are not sufficiently separated by centrifugation and filtration. Further purification was employed during each process step in the conversion of coal solution into graphite. Different methods of purification were employed in this study. They included chlorination, acid treatment and the ion-exchange or complexation method. Chlorine gas and hexachlorocyclohexane (benzene hexachloride) were used in the chlorination method. Acids such as hydrochloric, hydrofluoric and ascorbic were used in acid treatment. In the ion-exchange method, reagents such as methane, starch, potassium cyanide, ethylene-diaminetetraacetic acid, sodium fluoride, sodium sulphate, ice, glycerol and sodium nitrate were used. All the treated Refcoal was coked at 1 000º C. Pyrolysis was applied in other methods with the aim of volatilising elements that form volatile halides at higher temperatures. Analysis was done for elements such as calcium, cobalt, europium, gadolinium, lithium, sodium, silicon, thorium and uranium, and other elements in the periodic table. Inductively coupled plasma mass spectroscopy and inductively coupled plasma optical emission spectroscopy were used to analyse the concentrations of the trace elements in the coal (treated and untreated) and the coked Refcoal. In inductively coupled plasma mass spectroscopy, microwave digestion and fusion were applied as methods of preparation. However, the instrumentation gave different results for the same sample. The results showed that specific methods work for specific elements. The chlorination method and the… Advisors/Committee Members: Dr D L Morgan (advisor).

Subjects/Keywords: Purification; Nuclear graphite; Fusion reactors; Nuclear materials; UCTD

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Phupheli, M. (2008). Purifying coal for the production of nuclear graphite. (Masters Thesis). University of Pretoria. Retrieved from http://hdl.handle.net/2263/24051

Chicago Manual of Style (16^th Edition):

Phupheli, Milingoni. “Purifying coal for the production of nuclear graphite.” 2008. Masters Thesis, University of Pretoria. Accessed April 11, 2021. http://hdl.handle.net/2263/24051.

MLA Handbook (7^th Edition):

Phupheli, Milingoni. “Purifying coal for the production of nuclear graphite.” 2008. Web. 11 Apr 2021.

Vancouver:

Phupheli M. Purifying coal for the production of nuclear graphite. [Internet] [Masters thesis]. University of Pretoria; 2008. [cited 2021 Apr 11]. Available from: http://hdl.handle.net/2263/24051.

Council of Science Editors:

Phupheli M. Purifying coal for the production of nuclear graphite. [Masters Thesis]. University of Pretoria; 2008. Available from: http://hdl.handle.net/2263/24051

Michigan State University

18. Nguyen, Ngoc Bích. Investigation of the triple-alpha reaction in a full three-body approach.

Degree: 2013, Michigan State University

URL: http://etd.lib.msu.edu/islandora/object/etd:260

►

Thesis Ph. D. Michigan State University. Physics 2013.

We have developed a new three-body method to compute the triple-alpha reaction rate at low temperatures where… (more)

▼

Thesis Ph. D. Michigan State University. Physics 2013.

We have developed a new three-body method to compute the triple-alpha reaction rate at low temperatures where measurements are impossible and many numerical attempts have failed before. In this work, the triple-alpha is modeled as a three-body Borromean system in hyperspherical harmonics coordinates. In the low temperature region, the triple-alpha proceeds through a quadrupole transition from the 0⁺ continuum to the 2⁺₁ bound state in ¹²C. The 2⁺₁ bound state is obtained by solving a set of coupled channels equations in hyper-radius coordinates for negative energy with a boundary condition that requires the wavefunction to go to zero at large distances. The same approach can not be applied to the 0⁺ continuum state because it requires an exact boundary condition for the three charged particles. We therefore combine the R-matrix expansion, the R-matrix propagation method, and the screening technique in the hyperspherical harmonics basis to obtain a numerically stable three-body continuum wavefunction for the &alpha+&alpha+&alpha system. We employ the Ali-Bodmer potential for the alpha-alpha interaction which reproduces the low energy phase shifts as well as the 0⁺ resonance of ⁸Be. We add a three-body force to fit experimental data. Both the 2⁺₁ bound state and the 0⁺₂ resonant state in ¹²C are well reproduced in our framework. We find a dominant triangle three-alpha configuration for the Hoyle resonance by studying the density distribution function. The resonant and non-resonant continuum states of ¹²C( 0⁺) are obtained simultaneously, allowing us to include these two processes on the same footing. Long range Coulomb interactions show important effects especially in the low temperature regime. We also present a detailed convergence study of the triple-alpha reaction rate with respect to the screening radius and the size of the model space. The new rate agrees with the NACRE rate for temperatures greater than 0.07 GK, but a large enhancement at lower temperatures is found (&sim 10¹² at 0.02 GK). We observe a transition between dominance of the non-resonant versus the resonant triple-alpha capture process around 0.06 GK. Our results are then compared to previous calculations where additional approximations were made. We also explore the impact in astrophysics namely, in stellar evolution, helium accreting white dwarfs, and helium accreting neutron stars.The presence of very narrow two-body and three-body resonances in addition to the strong, long-range Coulomb interaction makes the triple-alpha problem very challenging. Our framework which is the combination of various methods is a new approach to overcome the well known difficulty of the three charged-particle system. This method is particularly suited to the very low energy…

Advisors/Committee Members: Nunes, Filomena M, Brown, Edward, Schatz, Hendrik, Danielewicz, Pawel, Mahanti, Subhendra.

Subjects/Keywords: Nuclear fusion; Helium at low temperatures; Stars – Evolution; Nuclear physics

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APA (6^th Edition):

Nguyen, N. B. (2013). Investigation of the triple-alpha reaction in a full three-body approach. (Thesis). Michigan State University. Retrieved from http://etd.lib.msu.edu/islandora/object/etd:260

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Nguyen, Ngoc Bích. “Investigation of the triple-alpha reaction in a full three-body approach.” 2013. Thesis, Michigan State University. Accessed April 11, 2021. http://etd.lib.msu.edu/islandora/object/etd:260.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Nguyen, Ngoc Bích. “Investigation of the triple-alpha reaction in a full three-body approach.” 2013. Web. 11 Apr 2021.

Vancouver:

Nguyen NB. Investigation of the triple-alpha reaction in a full three-body approach. [Internet] [Thesis]. Michigan State University; 2013. [cited 2021 Apr 11]. Available from: http://etd.lib.msu.edu/islandora/object/etd:260.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Nguyen NB. Investigation of the triple-alpha reaction in a full three-body approach. [Thesis]. Michigan State University; 2013. Available from: http://etd.lib.msu.edu/islandora/object/etd:260

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Michigan State University

19. Wu, Jian-qun. Subbarrier fusion in light and medium heavy systems.

Degree: PhD, Department of Physics and Astronomy, 1986, Michigan State University

URL: http://etd.lib.msu.edu/islandora/object/etd:41149

Subjects/Keywords: Nuclear fusion; Nuclear physics

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APA (6^th Edition):

Wu, J. (1986). Subbarrier fusion in light and medium heavy systems. (Doctoral Dissertation). Michigan State University. Retrieved from http://etd.lib.msu.edu/islandora/object/etd:41149

Chicago Manual of Style (16^th Edition):

Wu, Jian-qun. “Subbarrier fusion in light and medium heavy systems.” 1986. Doctoral Dissertation, Michigan State University. Accessed April 11, 2021. http://etd.lib.msu.edu/islandora/object/etd:41149.

MLA Handbook (7^th Edition):

Wu, Jian-qun. “Subbarrier fusion in light and medium heavy systems.” 1986. Web. 11 Apr 2021.

Vancouver:

Wu J. Subbarrier fusion in light and medium heavy systems. [Internet] [Doctoral dissertation]. Michigan State University; 1986. [cited 2021 Apr 11]. Available from: http://etd.lib.msu.edu/islandora/object/etd:41149.

Council of Science Editors:

Wu J. Subbarrier fusion in light and medium heavy systems. [Doctoral Dissertation]. Michigan State University; 1986. Available from: http://etd.lib.msu.edu/islandora/object/etd:41149

20. Dirceu Pereira. Fusão nucelar e secção de choque total de reação para o sistema 27Al + 16O.

Degree: 1979, University of São Paulo

URL: http://www.teses.usp.br/teses/disponiveis/43/43131/tde-10122013-150846/

►

Neste trabalho são apresentadas medidas das secções de choque de fusão nuclear para o sistema ANTPOT 27 Al + ANTPOT. 16 0,nas energias de bombardeio… (more)

Subjects/Keywords: Fusão nuclear; Nuclear fusion

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APA (6^th Edition):

Pereira, D. (1979). Fusão nucelar e secção de choque total de reação para o sistema 27Al + 16O. (Doctoral Dissertation). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/43/43131/tde-10122013-150846/

Chicago Manual of Style (16^th Edition):

Pereira, Dirceu. “Fusão nucelar e secção de choque total de reação para o sistema 27Al + 16O.” 1979. Doctoral Dissertation, University of São Paulo. Accessed April 11, 2021. http://www.teses.usp.br/teses/disponiveis/43/43131/tde-10122013-150846/.

MLA Handbook (7^th Edition):

Pereira, Dirceu. “Fusão nucelar e secção de choque total de reação para o sistema 27Al + 16O.” 1979. Web. 11 Apr 2021.

Vancouver:

Pereira D. Fusão nucelar e secção de choque total de reação para o sistema 27Al + 16O. [Internet] [Doctoral dissertation]. University of São Paulo; 1979. [cited 2021 Apr 11]. Available from: http://www.teses.usp.br/teses/disponiveis/43/43131/tde-10122013-150846/.

Council of Science Editors:

Pereira D. Fusão nucelar e secção de choque total de reação para o sistema 27Al + 16O. [Doctoral Dissertation]. University of São Paulo; 1979. Available from: http://www.teses.usp.br/teses/disponiveis/43/43131/tde-10122013-150846/

University of Manchester

21. Dawson, Huw Bacca Awesome. Friction Stir Welding of ODS Steels for Future Generation Nuclear Reactors.

Degree: 2018, University of Manchester

URL: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:312793

► In this project, we have successfully joined MA956 Oxide Dispersion-Strengthened (ODS) steel plates using Friction Stir Welding (FSW). ODS steels are prime candidate materials for… (more)

▼ In this project, we have successfully joined MA956 Oxide Dispersion-Strengthened (ODS) steel plates using Friction Stir Welding (FSW). ODS steels are prime candidate materials for the fuel cladding in Generation IV nuclear fission reactors and as first wall components in nuclear fusion reactors. This is due to their exhibiting excellent high temperature strength and creep behaviour, together with enhanced resistance to radiationinduced void swelling. ODS steels are heavily reliant on a fine dispersion of (Y-Al-O) nanooxide particles to provide the aforementioned properties. This, however, makes ODS steels particularly problematic to join. Most joining techniques melt the material along the joint line, but this would severely alter or deplete the nano-oxide dispersion and hence be highly detrimental to the materialâ€™s performance in a nuclear environment. FSW is a solid-state joining technique, and therefore can join ODS steel without melting the material. Although FSW can potentially alter the microstructure of the base material and affect the distribution of nano-oxide particles, if a sufficient number of nano-sized particles and a sufficiently homogeneous dispersion remain after the welding process, then a major roadblock for the implementation of ODS steels will have been removed. The research of this thesis focused on the impact of FSW on: i) the microstructure, ii) the mechanical properties, iii) the residual stresses, and iv) the abnormal grain growth behaviour of ODS steels; utilizing a wide array of techniques to assess the micro-to-nano scale structure and the properties of the base material and welds, including optical, scanning and transmission and electron microscopy, X-ray and neutron diffraction, small-angle neutron scattering, tensile testing and micro-hardness measurements. We also produced welds with systematic changes to the tool traverse speed and rotation speed to investigate the impact of changing the welding parameters on the weld microstructure, and therefore optimise the process parameters for enhanced radiation and mechanical performance of the ODS steel welds. Advisors/Committee Members: BURKE, MARY MG, Jimenez-Melero, Enrique, Burke, Mary.

Subjects/Keywords: ODS Steel; MA956; Nuclear Fusion; Nuclear Fission; Friction Stir Welding; Nuclear structural materials

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Dawson, H. B. A. (2018). Friction Stir Welding of ODS Steels for Future Generation Nuclear Reactors. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:312793

Chicago Manual of Style (16^th Edition):

Dawson, Huw Bacca Awesome. “Friction Stir Welding of ODS Steels for Future Generation Nuclear Reactors.” 2018. Doctoral Dissertation, University of Manchester. Accessed April 11, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:312793.

MLA Handbook (7^th Edition):

Dawson, Huw Bacca Awesome. “Friction Stir Welding of ODS Steels for Future Generation Nuclear Reactors.” 2018. Web. 11 Apr 2021.

Vancouver:

Dawson HBA. Friction Stir Welding of ODS Steels for Future Generation Nuclear Reactors. [Internet] [Doctoral dissertation]. University of Manchester; 2018. [cited 2021 Apr 11]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:312793.

Council of Science Editors:

Dawson HBA. Friction Stir Welding of ODS Steels for Future Generation Nuclear Reactors. [Doctoral Dissertation]. University of Manchester; 2018. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:312793

22. Dawson, Huw. Friction stir welding of ODS steels for future generation nuclear reactors.

Degree: PhD, 2018, University of Manchester

URL: https://www.research.manchester.ac.uk/portal/en/theses/friction-stir-welding-of-ods-steels-for-future-generation-nuclear-reactors(2603016f-6763-43d1-98ef-753e110b8791).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.740327

► In this project, we have successfully joined MA956 Oxide Dispersion-Strengthened (ODS) steel plates using Friction Stir Welding (FSW). ODS steels are prime candidate materials for… (more)

▼ In this project, we have successfully joined MA956 Oxide Dispersion-Strengthened (ODS) steel plates using Friction Stir Welding (FSW). ODS steels are prime candidate materials for the fuel cladding in Generation IV nuclear fission reactors and as first wall components in nuclear fusion reactors. This is due to their exhibiting excellent high temperature strength and creep behaviour, together with enhanced resistance to radiationinduced void swelling. ODS steels are heavily reliant on a fine dispersion of (Y-Al-O) nanooxide particles to provide the aforementioned properties. This, however, makes ODS steels particularly problematic to join. Most joining techniques melt the material along the joint line, but this would severely alter or deplete the nano-oxide dispersion and hence be highly detrimental to the materialâs performance in a nuclear environment. FSW is a solid-state joining technique, and therefore can join ODS steel without melting the material. Although FSW can potentially alter the microstructure of the base material and affect the distribution of nano-oxide particles, if a sufficient number of nano-sized particles and a sufficiently homogeneous dispersion remain after the welding process, then a major roadblock for the implementation of ODS steels will have been removed. The research of this thesis focused on the impact of FSW on: i) the microstructure, ii) the mechanical properties, iii) the residual stresses, and iv) the abnormal grain growth behaviour of ODS steels; utilizing a wide array of techniques to assess the micro-to-nano scale structure and the properties of the base material and welds, including optical, scanning and transmission and electron microscopy, X-ray and neutron diffraction, small-angle neutron scattering, tensile testing and micro-hardness measurements. We also produced welds with systematic changes to the tool traverse speed and rotation speed to investigate the impact of changing the welding parameters on the weld microstructure, and therefore optimise the process parameters for enhanced radiation and mechanical performance of the ODS steel welds.

Subjects/Keywords: 620; Friction Stir Welding; Nuclear structural materials; Nuclear Fission; Nuclear Fusion; MA956; ODS Steel

10 more images…

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APA (6^th Edition):

Dawson, H. (2018). Friction stir welding of ODS steels for future generation nuclear reactors. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/friction-stir-welding-of-ods-steels-for-future-generation-nuclear-reactors(2603016f-6763-43d1-98ef-753e110b8791).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.740327

Chicago Manual of Style (16^th Edition):

Dawson, Huw. “Friction stir welding of ODS steels for future generation nuclear reactors.” 2018. Doctoral Dissertation, University of Manchester. Accessed April 11, 2021. https://www.research.manchester.ac.uk/portal/en/theses/friction-stir-welding-of-ods-steels-for-future-generation-nuclear-reactors(2603016f-6763-43d1-98ef-753e110b8791).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.740327.

MLA Handbook (7^th Edition):

Dawson, Huw. “Friction stir welding of ODS steels for future generation nuclear reactors.” 2018. Web. 11 Apr 2021.

Vancouver:

Dawson H. Friction stir welding of ODS steels for future generation nuclear reactors. [Internet] [Doctoral dissertation]. University of Manchester; 2018. [cited 2021 Apr 11]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/friction-stir-welding-of-ods-steels-for-future-generation-nuclear-reactors(2603016f-6763-43d1-98ef-753e110b8791).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.740327.

Council of Science Editors:

Dawson H. Friction stir welding of ODS steels for future generation nuclear reactors. [Doctoral Dissertation]. University of Manchester; 2018. Available from: https://www.research.manchester.ac.uk/portal/en/theses/friction-stir-welding-of-ods-steels-for-future-generation-nuclear-reactors(2603016f-6763-43d1-98ef-753e110b8791).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.740327

University of Rochester

23. Bose, Arijit (1988 - ). Direct drive inertial confinement fusion: analysis of the implosion core.

Degree: PhD, 2018, University of Rochester

URL: http://hdl.handle.net/1802/33324

► Direct laser-driven fusion uses multiple laser beams to symmetrically illuminate a frozen deuterium-tritium shell. The motive is to produce a hot conned central plasma|the core|which… (more)

▼ Direct laser-driven fusion uses multiple laser beams to symmetrically illuminate a frozen deuterium-tritium shell. The motive is to produce a hot conned central plasma|the core|which would initiate fusion reactions and lead to self-heating by alpha particle energy deposition. The OMEGA laser produces ~25-30 kJ of on-target energy, approximately 1.4% of the energy available on the National Ignition Facility (NIF). Currently, the NIF is not congured to perform symmetric illumination while the 60 beam OMEGA routinely irradiates targets symmetrically. To help motivate NIF to explore direct drive targets in a future symmetric illumination conguration, OMEGA experimental results and their scaling provide a valuable and cost-effective tool. This theoretical and numerical analysis shows that the experiments at the OMEGA [Regan et al., Phys. Rev. Lett. 117, 025001 (2016)] when hydrodynamically scaled to 1.9 MJ would produce several times the fusion energy output than that achieved with the highest performing indirectly driven targets at NIF [Hurricane et al, Nature 506, 343{348 (2014)]. In order to determine the optimal path to thermonuclear ignition, it is necessary to have a metric to estimate implosion performance and the level of alpha heating. A simple model describing the nal stage of inertial connement fusion (ICF) implosions and the performance metric is shown. The Rayleigh-Taylor instability (RTI) produces long- and mid-wavelength distortions of the core, which degrade the implosion performance. A theoretical analysis of the effect of the two types of asymmetries on the implosion hydrodynamics and fusion neutronics is discussed. The experimental observables for the high performing OMEGA implosions were analyzed for investigation of the degradation sources, this is essential for future improvements of the implosion quality. The analysis of several repeats of the cryogenic implosion experiments suggests a systematic degradation mechanism aecting the implosions. It is found that using a combination of the two types of asymmetries, all of the experimentally observed implosion core conditions could be simultaneously reproduced in simulations. The scaling of the core to NIF required developing a theoretical understanding of the scaling of the deceleration-phase RTI. The scaling of thermal conduction and radiation transport, which mitigate the RTI growth, is shown. It is found that the degradation of implosion performance caused by the RTI is similar for NIF and OMEGA. Using all of these, a general fusion-yield extrapolation procedure has been developed to estimate ICF implosion performance at higher laser energies. The scaling assumes only that the implosion hydrodynamic effciency is unchanged at higher energies, and relies solely on a volumetric scaling of the experimentally observed core conditions. Since the stagnation physics for conventional hot-spot ignition is equivalent for both direct- and indirect-drive, the technique, in general, can be applied to both. Using this, the OMEGA…

Subjects/Keywords: Alternative energy; Clean energy; Controlled nuclear fusion; Fusion power plant; Plasma physics

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APA (6^th Edition):

Bose, A. (. -. ). (2018). Direct drive inertial confinement fusion: analysis of the implosion core. (Doctoral Dissertation). University of Rochester. Retrieved from http://hdl.handle.net/1802/33324

Chicago Manual of Style (16^th Edition):

Bose, Arijit (1988 - ). “Direct drive inertial confinement fusion: analysis of the implosion core.” 2018. Doctoral Dissertation, University of Rochester. Accessed April 11, 2021. http://hdl.handle.net/1802/33324.

MLA Handbook (7^th Edition):

Bose, Arijit (1988 - ). “Direct drive inertial confinement fusion: analysis of the implosion core.” 2018. Web. 11 Apr 2021.

Vancouver:

Bose A(-). Direct drive inertial confinement fusion: analysis of the implosion core. [Internet] [Doctoral dissertation]. University of Rochester; 2018. [cited 2021 Apr 11]. Available from: http://hdl.handle.net/1802/33324.

Council of Science Editors:

Bose A(-). Direct drive inertial confinement fusion: analysis of the implosion core. [Doctoral Dissertation]. University of Rochester; 2018. Available from: http://hdl.handle.net/1802/33324

Texas A&M University

24. Mayorov, Dmitriy A. Synthesis of Shell-Stabilized Nuclides in Fusion-Evaporation Reactions Induced by 48Ca, 50Ti, or 54Cr Projectiles.

Degree: PhD, Chemistry, 2015, Texas A&M University

URL: http://hdl.handle.net/1969.1/155164

► Production cross sections of nuclides in the vicinity of the closed neutron shell at N = 126 were measured in heavy-ion fusion reactions with 154Gd,… (more)

Subjects/Keywords: Heavy-Ion Fusion Reactions; Nuclear Level Density; Fusion-Evaporation Theory; Synthesis of Heavy Elements.

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APA (6^th Edition):

Mayorov, D. A. (2015). Synthesis of Shell-Stabilized Nuclides in Fusion-Evaporation Reactions Induced by 48Ca, 50Ti, or 54Cr Projectiles. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/155164

Chicago Manual of Style (16^th Edition):

Mayorov, Dmitriy A. “Synthesis of Shell-Stabilized Nuclides in Fusion-Evaporation Reactions Induced by 48Ca, 50Ti, or 54Cr Projectiles.” 2015. Doctoral Dissertation, Texas A&M University. Accessed April 11, 2021. http://hdl.handle.net/1969.1/155164.

MLA Handbook (7^th Edition):

Mayorov, Dmitriy A. “Synthesis of Shell-Stabilized Nuclides in Fusion-Evaporation Reactions Induced by 48Ca, 50Ti, or 54Cr Projectiles.” 2015. Web. 11 Apr 2021.

Vancouver:

Mayorov DA. Synthesis of Shell-Stabilized Nuclides in Fusion-Evaporation Reactions Induced by 48Ca, 50Ti, or 54Cr Projectiles. [Internet] [Doctoral dissertation]. Texas A&M University; 2015. [cited 2021 Apr 11]. Available from: http://hdl.handle.net/1969.1/155164.

Council of Science Editors:

Mayorov DA. Synthesis of Shell-Stabilized Nuclides in Fusion-Evaporation Reactions Induced by 48Ca, 50Ti, or 54Cr Projectiles. [Doctoral Dissertation]. Texas A&M University; 2015. Available from: http://hdl.handle.net/1969.1/155164

25. Gracias, William Agnelo. The numerical study of filament dynamics in tokamak scrape-off layer plasmas : Etude de la dynamique des structures cohérentes filamentaires dans les plasmas de bord turbulents de tokamak par la simulation numérique.

Degree: Docteur es, Mécanique et physique des fluides, 2018, Aix-Marseille; Universidad Carlos III (Madrid)

URL: http://www.theses.fr/2018AIXM0731

►

La présence de structures filamentaires est souvent rapportée dans plusieurs machines de fusion nucléaire à confinement magnétique, spécialement sur lequel s'appelle Tokamak. Etant porteurs de… (more)

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La présence de structures filamentaires est souvent rapportée dans plusieurs machines de fusion nucléaire à confinement magnétique, spécialement sur lequel s'appelle Tokamak. Etant porteurs de grandes quantités des particules et chaleur, la présence des filaments dans le bord du tokamak (le scrape-off layer, SOL) pourraient poser des dangers aux superficies solides du tokamak. Pour mieux comprendre leur comportement, dans le cadre de cette thèse doctorale, les filaments sont étudiés par les expériences numériques en utilisant un modèle 3D fluide istherme, TOKAM3X en les considerant comme structures isolées et structures spontanées. Cette manière de les étudier permet de faire divers analyses paramétriques – par exemple la resistivité parallèle du plasma et la présence d'un cisaïllement magnétique, et au même temps les propriétés du filaments (comme sa longeur parallèle, et son intensité de densité). Ces études montrent un impact fort de la resistivité parallèle sur la velocité des filaments et en conséquence peut modifier leur temps de vie dans le bord de la machine. Les résultats des simulations sur le cisaïllement magnétique et la séparatrice indiquent qu'ils sont des ingrédients clés pour la destruction et génération des filaments. En plus, la comparaison entre les filaments initialisés (seeded) et les filaments formés spontanément montre qu'ils ne sont pas parreils dans leur comportement, bien que leurs characteristiques moyennées en temps sont bien conservées.

Filamentary transport has been experimentally observed in a multitude of magnetically confined fusion devices, especially of the tokamak type. Filaments are carriers of large quantities of particles and heat and as such, their presence in the SOL has implications for the target surface design in future fusion reactors. To better understand their nature, this doctoral thesis studies filaments through computer simulations as isolated structures and spontaneously forming structures, using a 3D fluid model called the TOKAM3X. Parametric studies using the model for studying the effect of the plasma's parallel resistivity and magnetic shear, and also the filament's parallel extension and size/density amplitude are performed and analysed. The studies reveal the strong impact of the parallel resistivity on filament velocities and hence their lifetimes in the SOL. The doctoral work also looked at the impact of strong local magnetic shear and the separatrix on the motion and generation of filaments. The results from the simulations performed reveal that strong shear mechanisms may be key to the destruction and formation of filaments. Further, a comparison of spontaneously forming and seeded filaments shows that seeded filaments do not behave completely the same way as spontaneously forming ones. But their mean velocity characteristics are still retained to a good degree.

Advisors/Committee Members: Serre, Eric (thesis director), García Gonzalo, Luis (thesis director), Pitts, Richard A. (thesis director).

Subjects/Keywords: Sol; Tokamak; Bord; Filaments; Blobs; Fusion nucléaire; Nuclear fusion; Tokamak; Edge; Filaments; Sol; Blobs

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Gracias, W. A. (2018). The numerical study of filament dynamics in tokamak scrape-off layer plasmas : Etude de la dynamique des structures cohérentes filamentaires dans les plasmas de bord turbulents de tokamak par la simulation numérique. (Doctoral Dissertation). Aix-Marseille; Universidad Carlos III (Madrid). Retrieved from http://www.theses.fr/2018AIXM0731

Chicago Manual of Style (16^th Edition):

Gracias, William Agnelo. “The numerical study of filament dynamics in tokamak scrape-off layer plasmas : Etude de la dynamique des structures cohérentes filamentaires dans les plasmas de bord turbulents de tokamak par la simulation numérique.” 2018. Doctoral Dissertation, Aix-Marseille; Universidad Carlos III (Madrid). Accessed April 11, 2021. http://www.theses.fr/2018AIXM0731.

MLA Handbook (7^th Edition):

Gracias, William Agnelo. “The numerical study of filament dynamics in tokamak scrape-off layer plasmas : Etude de la dynamique des structures cohérentes filamentaires dans les plasmas de bord turbulents de tokamak par la simulation numérique.” 2018. Web. 11 Apr 2021.

Vancouver:

Gracias WA. The numerical study of filament dynamics in tokamak scrape-off layer plasmas : Etude de la dynamique des structures cohérentes filamentaires dans les plasmas de bord turbulents de tokamak par la simulation numérique. [Internet] [Doctoral dissertation]. Aix-Marseille; Universidad Carlos III (Madrid); 2018. [cited 2021 Apr 11]. Available from: http://www.theses.fr/2018AIXM0731.

Council of Science Editors:

Gracias WA. The numerical study of filament dynamics in tokamak scrape-off layer plasmas : Etude de la dynamique des structures cohérentes filamentaires dans les plasmas de bord turbulents de tokamak par la simulation numérique. [Doctoral Dissertation]. Aix-Marseille; Universidad Carlos III (Madrid); 2018. Available from: http://www.theses.fr/2018AIXM0731

26. Cunningham, Kevin Hawkins. Ductile-Phase-Toughened Tungsten for Plasma-Facing Materials.

Degree: 2015, University of California – eScholarship, University of California

URL: http://www.escholarship.org/uc/item/7664g3zj

► A variety of processing approaches were employed to fabricate ductile-phase-toughened (DPT) tungsten (W) composites. Mechanical testing and analytical modeling were used to guide composite development.… (more)

▼ A variety of processing approaches were employed to fabricate ductile-phase-toughened (DPT) tungsten (W) composites. Mechanical testing and analytical modeling were used to guide composite development. This work provides a basis for further development of W composites to be used in structural divertor components of future fusion reactors.W wire was tested in tension, showing significant ductility and strength. Coatings of copper (Cu) or tungsten carbide (WC) were applied to the W wire via electrodeposition and carburization, respectively. Composites were fabricated using spark plasma sintering (SPS) to consolidate W powders together with each type of coated W wire. DPT behavior, e.g. crack arrest and crack bridging, was not observed in three-point bend testing of the sintered composites.A laminate was fabricated by hot pressing W and Cu foils together with W wires, and subsequently tested in tension. This laminate was bonded via hot pressing to thick W plate as a reinforcing layer, and the composite was tested in three-point bending. Crack arrest was observed along with some fiber pullout, but significant transverse cracking in the W plate confounded further fracture toughness analysis.The fracture toughness of thin W plate was measured in three-point bending. W plates were brazed with Cu foils to form a laminate. Crack arrest and crack bridging were observed in three-point bend tests of the laminate, and fracture resistance curves were successfully calculated for this DPT composite.An analytical model of crack bridging was developed using the basis described by Chao in previous work by the group. The model uses the specimen geometry, matrix properties, and the stress-displacement function of a ductile reinforcement (“bridging law”) to calculate the fracture resistance curve (R-curve) and load-displacement curve (P-D curve) for any test specimen geometry. The code was also implemented to estimate the bridging law of an arbitrary composite using R-curve data.Finally, a parametric study was performed to quantitatively determine the necessary mechanical properties of useful toughening reinforcements for a DPT W composite. The analytical model has a broad applicability for any DPT material.

Subjects/Keywords: Materials Science; Nuclear engineering; Engineering; Composites; Fracture mechanics; Modeling; Nuclear fusion; Tungsten

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APA (6^th Edition):

Cunningham, K. H. (2015). Ductile-Phase-Toughened Tungsten for Plasma-Facing Materials. (Thesis). University of California – eScholarship, University of California. Retrieved from http://www.escholarship.org/uc/item/7664g3zj

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Cunningham, Kevin Hawkins. “Ductile-Phase-Toughened Tungsten for Plasma-Facing Materials.” 2015. Thesis, University of California – eScholarship, University of California. Accessed April 11, 2021. http://www.escholarship.org/uc/item/7664g3zj.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Cunningham, Kevin Hawkins. “Ductile-Phase-Toughened Tungsten for Plasma-Facing Materials.” 2015. Web. 11 Apr 2021.

Vancouver:

Cunningham KH. Ductile-Phase-Toughened Tungsten for Plasma-Facing Materials. [Internet] [Thesis]. University of California – eScholarship, University of California; 2015. [cited 2021 Apr 11]. Available from: http://www.escholarship.org/uc/item/7664g3zj.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Cunningham KH. Ductile-Phase-Toughened Tungsten for Plasma-Facing Materials. [Thesis]. University of California – eScholarship, University of California; 2015. Available from: http://www.escholarship.org/uc/item/7664g3zj

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Missouri University of Science and Technology

27. Pillai, Nishant Raghav. Analysis of energy economy in muon catalyzed fusion considering external x-ray reactivation.

Degree: M.S. in Nuclear Engineering, Nuclear Engineering, Missouri University of Science and Technology

URL: https://scholarsmine.mst.edu/masters_theses/7933

► "An analysis of the energy economy of a theoretical muon-catalyzed nuclear fusion system has been made by invoking the use of point kinetic equations, Monte… (more)

Subjects/Keywords: Fusion; MCNP; Muon; Nuclear; Nuclear Engineering

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Pillai, N. R. (n.d.). Analysis of energy economy in muon catalyzed fusion considering external x-ray reactivation. (Masters Thesis). Missouri University of Science and Technology. Retrieved from https://scholarsmine.mst.edu/masters_theses/7933

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Chicago Manual of Style (16^th Edition):

Pillai, Nishant Raghav. “Analysis of energy economy in muon catalyzed fusion considering external x-ray reactivation.” Masters Thesis, Missouri University of Science and Technology. Accessed April 11, 2021. https://scholarsmine.mst.edu/masters_theses/7933.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

MLA Handbook (7^th Edition):

Pillai, Nishant Raghav. “Analysis of energy economy in muon catalyzed fusion considering external x-ray reactivation.” Web. 11 Apr 2021.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Vancouver:

Pillai NR. Analysis of energy economy in muon catalyzed fusion considering external x-ray reactivation. [Internet] [Masters thesis]. Missouri University of Science and Technology; [cited 2021 Apr 11]. Available from: https://scholarsmine.mst.edu/masters_theses/7933.

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Council of Science Editors:

Pillai NR. Analysis of energy economy in muon catalyzed fusion considering external x-ray reactivation. [Masters Thesis]. Missouri University of Science and Technology; Available from: https://scholarsmine.mst.edu/masters_theses/7933

Note: this citation may be lacking information needed for this citation format:
No year of publication.

Ohio University

28. Parker, Cody E. The ³H(d,γ) Reaction and the ³H(d,γ)/ ³H(d,n) Branching Ratio for E_c.m. ≤ 300 keV.

Degree: PhD, Physics and Astronomy (Arts and Sciences), 2016, Ohio University

URL: http://rave.ohiolink.edu/etdc/view?acc_num=ohiou1471366054

► The ³H(d,γ)⁵He reaction and the ³H(d,γ)/ ³H(d,n) branching ratio have been measured using a 500–keV pulsed deuteron beam incident on a titanium tritide target of… (more)

Subjects/Keywords: Nuclear Physics; nuclear fusion reaction; radiative capture; tritium; gamma-ray spectroscopy; DT-gamma

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APA (6^th Edition):

Parker, C. E. (2016). The ³H(d,γ) Reaction and the ³H(d,γ)/ ³H(d,n) Branching Ratio for E_c.m. ≤ 300 keV. (Doctoral Dissertation). Ohio University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=ohiou1471366054

Chicago Manual of Style (16^th Edition):

Parker, Cody E. “The ³H(d,γ) Reaction and the ³H(d,γ)/ ³H(d,n) Branching Ratio for E_c.m. ≤ 300 keV.” 2016. Doctoral Dissertation, Ohio University. Accessed April 11, 2021. http://rave.ohiolink.edu/etdc/view?acc_num=ohiou1471366054.

MLA Handbook (7^th Edition):

Parker, Cody E. “The ³H(d,γ) Reaction and the ³H(d,γ)/ ³H(d,n) Branching Ratio for E_c.m. ≤ 300 keV.” 2016. Web. 11 Apr 2021.

Vancouver:

Parker CE. The ³H(d,γ) Reaction and the ³H(d,γ)/ ³H(d,n) Branching Ratio for E_c.m. ≤ 300 keV. [Internet] [Doctoral dissertation]. Ohio University; 2016. [cited 2021 Apr 11]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=ohiou1471366054.

Council of Science Editors:

Parker CE. The ³H(d,γ) Reaction and the ³H(d,γ)/ ³H(d,n) Branching Ratio for E_c.m. ≤ 300 keV. [Doctoral Dissertation]. Ohio University; 2016. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=ohiou1471366054

29. Bardaji, Júlio Bialkowski. Um sistema de reações acopladas de fissão e fusão nuclear : a influência do processo de fusão no deslocamento da meia vida dos produtos de fissão.

Degree: 2013, Brazil

URL: http://hdl.handle.net/10183/85043

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O objetivo dessa dissertação foi analisar a influência de possíveis reações de fusão nuclear quando elementos leves, definidos como alvos são adicionados ao combustível nuclear.… (more)

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O objetivo dessa dissertação foi analisar a influência de possíveis reações de fusão nuclear quando elementos leves, definidos como alvos são adicionados ao combustível nuclear. A energia cinética dos produtos de fissão, na concepção desse estudo, é utilizada para vencer a repulsão elétrica entre os núcleos. Para esse trabalho foram considerados a adição de hidrogênio, deutério, lítio e berílio em fração mássica de 0,30. A escolha desses elementos foi realizada através da análise da energia de ligação, do número atômico e das seções de choque experimentais de fusão. A avaliação da fusão nuclear foi realizada via principio da incerteza, pois não há um modelo que pudesse cobrir um grande número de reações possíveis. A probabilidade de reação foi aproximada como uma função da probabilidade de um produto de fissão encontrar determinado elemento leve. Adicionalmente foram calculados os tempos de freamento eletrônico para os produtos de fissão com isso verificou-se que a escala de freamento não representa limitação para a fusão. A principal alteração, devido à adição dos alvos, foi na distribuição dos tempos de meia vida dos produtos de fissão, na direção de maiores tempos. A alteração nessa grandeza indica que é possível reduzir a atividade média do rejeito nuclear, em especial o de alto nível de radioatividade, tornando sua manipulação mais segura. Os alvos de hidrogênio e lítio apresentaram os melhores resultados para o aumento do tempo de meia vida médio dos produtos de fissão, conseguindo altera-la em média duas ordens de grandeza. Outras alterações, que não foram alvo desse estudo, são esperadas devido à inserção desses alvos, como por exemplo, na cinética.

The objective of this dissertation was to analyze the influence of possible nuclear fusion reactions when light elements, defined as targets are added to the nuclear fuel. The kinetic energy of the fission products, in the conception of this study, is used to overcome the electrical repulsion between the nuclei. For this work were considered the addition of hydrogen, deuterium, lithium and beryllium in mass fraction of 0.30. The choice of these elements was performed by analyzing the binding energy, the atomic number and experimental fusion cross sections. The assessment of fusion was performed via the uncertainty principle, since there is no model that could cover a large number of possible reactions. The probability of reaction was approximated as a function of the probability of fission product find a particular light element. Additionally times were calculated for the electronic stopping fission products where was found that scale of stopping does not impose limits on fusion. The main change due to the addition of the targets was the distribution of halflives of the fission products, towards longer times. The change in this magnitude indicates that it is possible to reduce the average activity of the nuclear waste, in particular the high level of radioactivity, making handling safer. The targets of hydrogen and lithium showed the best results for increasing…

Advisors/Committee Members: Bodmann, Bardo Ernst Josef.

Subjects/Keywords: Fusão nuclear; Fenômenos de transporte; Energia nuclear; Fusion; Fission products; Half-life

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Bardaji, J. B. (2013). Um sistema de reações acopladas de fissão e fusão nuclear : a influência do processo de fusão no deslocamento da meia vida dos produtos de fissão. (Masters Thesis). Brazil. Retrieved from http://hdl.handle.net/10183/85043

Chicago Manual of Style (16^th Edition):

Bardaji, Júlio Bialkowski. “Um sistema de reações acopladas de fissão e fusão nuclear : a influência do processo de fusão no deslocamento da meia vida dos produtos de fissão.” 2013. Masters Thesis, Brazil. Accessed April 11, 2021. http://hdl.handle.net/10183/85043.

MLA Handbook (7^th Edition):

Bardaji, Júlio Bialkowski. “Um sistema de reações acopladas de fissão e fusão nuclear : a influência do processo de fusão no deslocamento da meia vida dos produtos de fissão.” 2013. Web. 11 Apr 2021.

Vancouver:

Bardaji JB. Um sistema de reações acopladas de fissão e fusão nuclear : a influência do processo de fusão no deslocamento da meia vida dos produtos de fissão. [Internet] [Masters thesis]. Brazil; 2013. [cited 2021 Apr 11]. Available from: http://hdl.handle.net/10183/85043.

Council of Science Editors:

Bardaji JB. Um sistema de reações acopladas de fissão e fusão nuclear : a influência do processo de fusão no deslocamento da meia vida dos produtos de fissão. [Masters Thesis]. Brazil; 2013. Available from: http://hdl.handle.net/10183/85043

University of California – Berkeley

30. Sit, Roger Carson. Investigation of the Feasibility of a Small Scale Transmutation Device.

Degree: Nuclear Engineering, 2009, University of California – Berkeley

URL: http://www.escholarship.org/uc/item/9j62k03p

► This dissertation presents the design and feasibility of a small-scale, fusion-based transmutation device incorporating a commercially available neutron generator. It also presents the design features… (more)

▼ This dissertation presents the design and feasibility of a small-scale, fusion-based transmutation device incorporating a commercially available neutron generator. It also presents the design features necessary to optimize the device and render it practical for the transmutation of selected long-lived fission products and actinides.Four conceptual designs of a transmutation device were used to study the transformation of seven radionuclides: long-lived fission products (Tc-99 and I-129), short-lived fission products (Cs-137 and Sr-90), and selective actinides (Am-241, Pu-238, and Pu-239). These radionuclides were chosen because they are major components of spent nuclear fuel and also because they exist as legacy sources that are being stored pending a decision regarding their ultimate disposition.The four designs include the use of two different devices; a Deuterium-Deuterium (D-D) neutron generator (for one design) and a Deuterium-Tritium (D-T) neutron generator (for three designs) in configurations which provide different neutron energy spectra for targeting the radionuclide for transmutation. Key parameters analyzed include total fluence and flux requirements; transmutation effectiveness measured as irradiation effective half-life; and activation products generated along with their characteristics: activity, dose rate, decay, and ingestion and inhalation radiotoxicity.From this investigation, conclusions were drawn about the feasibility of the device, the design and technology enhancements that would be required to make transmutation practical, the most beneficial design for each radionuclide, the consequence of the transmutation, and radiation protection issues that are important for the conceptual design of the transmutation device.Key conclusions from this investigation include: (1) the transmutation of long-lived fission products and select actinides can be practical using a small-scale, fusion driven transmutation device; (2) the transmutation of long-lived fission products could result in an irradiation effective half-life of a few years with a three order magnitude increase in the on-target neutron flux accomplishable through a combination of technological enhancements to the source and system design optimization; (3) the transmutation of long-lived fission products requires a thermal-slow energy spectrum to prevent the generation of activation products with half-lives even longer than the original radionuclide; (4) there is no benefit in trying to transmute short-lived fission products due to the ineffectiveness of the transmutation process and the generation of a multiplicity of counterproductive activation products; (5) for actinides, irradiation effective half-lives of < 1 year can be achieved with a four orders magnitude increase in the on-target flux; (6) the ideal neutron energy spectra for transmuting actinides is highly dependent on the particular radionuclide and its fission-to-capture ratio as they determine the generation rate of other actinides; and (7) the methodology developed in this…

Subjects/Keywords: Engineering, Nuclear; compact neutron generator; D-T fusion neutrons; Transmutation

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Sit, R. C. (2009). Investigation of the Feasibility of a Small Scale Transmutation Device. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/9j62k03p

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Sit, Roger Carson. “Investigation of the Feasibility of a Small Scale Transmutation Device.” 2009. Thesis, University of California – Berkeley. Accessed April 11, 2021. http://www.escholarship.org/uc/item/9j62k03p.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Sit, Roger Carson. “Investigation of the Feasibility of a Small Scale Transmutation Device.” 2009. Web. 11 Apr 2021.

Vancouver:

Sit RC. Investigation of the Feasibility of a Small Scale Transmutation Device. [Internet] [Thesis]. University of California – Berkeley; 2009. [cited 2021 Apr 11]. Available from: http://www.escholarship.org/uc/item/9j62k03p.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Sit RC. Investigation of the Feasibility of a Small Scale Transmutation Device. [Thesis]. University of California – Berkeley; 2009. Available from: http://www.escholarship.org/uc/item/9j62k03p

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

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Open Access Theses and Dissertations