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You searched for subject:(Fission gases). Showing records 1 – 10 of 10 total matches.

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University of Missouri – Columbia

1. Wilson, Jason. Transport of helium and fission product gases in porous/fractured geometry.

Degree: 2012, University of Missouri – Columbia

 [ACCESS RESTRICTED TO THE UNIVERSITY OF MISSOURI AT AUTHOR'S REQUEST.] Measuring and quantifying the transport of helium and fission products in reactor materials is a… (more)

Subjects/Keywords: very high temperature reactors; safety issues; fission gases; porous media

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APA (6th Edition):

Wilson, J. (2012). Transport of helium and fission product gases in porous/fractured geometry. (Thesis). University of Missouri – Columbia. Retrieved from http://hdl.handle.net/10355/15924

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

Chicago Manual of Style (16th Edition):

Wilson, Jason. “Transport of helium and fission product gases in porous/fractured geometry.” 2012. Thesis, University of Missouri – Columbia. Accessed April 21, 2019. http://hdl.handle.net/10355/15924.

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

MLA Handbook (7th Edition):

Wilson, Jason. “Transport of helium and fission product gases in porous/fractured geometry.” 2012. Web. 21 Apr 2019.

Vancouver:

Wilson J. Transport of helium and fission product gases in porous/fractured geometry. [Internet] [Thesis]. University of Missouri – Columbia; 2012. [cited 2019 Apr 21]. Available from: http://hdl.handle.net/10355/15924.

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

Council of Science Editors:

Wilson J. Transport of helium and fission product gases in porous/fractured geometry. [Thesis]. University of Missouri – Columbia; 2012. Available from: http://hdl.handle.net/10355/15924

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


Delft University of Technology

2. Damen, P.M.G. Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation.

Degree: 2003, Delft University of Technology

 In order to reduce the long-term radiotoxicity of spent nuclear fuel, many studies are performed on partitioning and transmutation of actinides. In such a scenario,… (more)

Subjects/Keywords: actinide transmutation; fission gases; helium

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APA (6th Edition):

Damen, P. M. G. (2003). Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation. (Doctoral Dissertation). Delft University of Technology. Retrieved from http://resolver.tudelft.nl/uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; urn:NBN:nl:ui:24-uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; urn:NBN:nl:ui:24-uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; http://resolver.tudelft.nl/uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20

Chicago Manual of Style (16th Edition):

Damen, P M G. “Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation.” 2003. Doctoral Dissertation, Delft University of Technology. Accessed April 21, 2019. http://resolver.tudelft.nl/uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; urn:NBN:nl:ui:24-uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; urn:NBN:nl:ui:24-uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; http://resolver.tudelft.nl/uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20.

MLA Handbook (7th Edition):

Damen, P M G. “Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation.” 2003. Web. 21 Apr 2019.

Vancouver:

Damen PMG. Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation. [Internet] [Doctoral dissertation]. Delft University of Technology; 2003. [cited 2019 Apr 21]. Available from: http://resolver.tudelft.nl/uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; urn:NBN:nl:ui:24-uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; urn:NBN:nl:ui:24-uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; http://resolver.tudelft.nl/uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20.

Council of Science Editors:

Damen PMG. Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation. [Doctoral Dissertation]. Delft University of Technology; 2003. Available from: http://resolver.tudelft.nl/uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; urn:NBN:nl:ui:24-uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; urn:NBN:nl:ui:24-uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20 ; http://resolver.tudelft.nl/uuid:ec290f3e-5d94-447d-98ac-eb8659a12b20

3. Cagna, Céline. Influence des gaz de fission sur l'état mécanique des combustibles oxydes irradiés : Influence of fission gases on the mechanical state of irradiated oxide fuels.

Degree: Docteur es, Mécanique-matériaux, 2016, Paris, ENSAM

L'irradiation génère dans le combustible des gaz de fission, principalement xénon et krypton, présents sous forme dissoute et sous forme de bulles. L’objectif de ces… (more)

Subjects/Keywords: Combustible nucléaire; Gaz de fission; Pression; Ebsd; Sims; Déformation; Nuclear fuel; Fission gases; Pressure; Ebsd; Sims; Strain

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APA (6th Edition):

Cagna, C. (2016). Influence des gaz de fission sur l'état mécanique des combustibles oxydes irradiés : Influence of fission gases on the mechanical state of irradiated oxide fuels. (Doctoral Dissertation). Paris, ENSAM. Retrieved from http://www.theses.fr/2016ENAM0033

Chicago Manual of Style (16th Edition):

Cagna, Céline. “Influence des gaz de fission sur l'état mécanique des combustibles oxydes irradiés : Influence of fission gases on the mechanical state of irradiated oxide fuels.” 2016. Doctoral Dissertation, Paris, ENSAM. Accessed April 21, 2019. http://www.theses.fr/2016ENAM0033.

MLA Handbook (7th Edition):

Cagna, Céline. “Influence des gaz de fission sur l'état mécanique des combustibles oxydes irradiés : Influence of fission gases on the mechanical state of irradiated oxide fuels.” 2016. Web. 21 Apr 2019.

Vancouver:

Cagna C. Influence des gaz de fission sur l'état mécanique des combustibles oxydes irradiés : Influence of fission gases on the mechanical state of irradiated oxide fuels. [Internet] [Doctoral dissertation]. Paris, ENSAM; 2016. [cited 2019 Apr 21]. Available from: http://www.theses.fr/2016ENAM0033.

Council of Science Editors:

Cagna C. Influence des gaz de fission sur l'état mécanique des combustibles oxydes irradiés : Influence of fission gases on the mechanical state of irradiated oxide fuels. [Doctoral Dissertation]. Paris, ENSAM; 2016. Available from: http://www.theses.fr/2016ENAM0033

4. Pacull, Julien. Modèle numérique micro-mécanique d'agrégat polycristallin pour le comportement des combustibles oxydes : Architecture of cognitive control within the cerebral cortex in schizophrenia.

Degree: Docteur es, Mécanique des Solides, 2011, Aix-Marseille 1

Dans les réacteurs nucléaires à eau sous-pression, le combustible est constitué de pastilles d’oxyde d’uranium (UO2), dont le comportement ne peut être simulé qu'à travers… (more)

Subjects/Keywords: Polycristal; Micromécanique; Homogénéisation; Décohésion intergranulaire; Combustible nucléaire; Produits de fission; Polycrystal; Micromechanics; Homogenization; Intergranular crack opening; Nuclear fuel; Fission gases

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APA (6th Edition):

Pacull, J. (2011). Modèle numérique micro-mécanique d'agrégat polycristallin pour le comportement des combustibles oxydes : Architecture of cognitive control within the cerebral cortex in schizophrenia. (Doctoral Dissertation). Aix-Marseille 1. Retrieved from http://www.theses.fr/2011AIX10021

Chicago Manual of Style (16th Edition):

Pacull, Julien. “Modèle numérique micro-mécanique d'agrégat polycristallin pour le comportement des combustibles oxydes : Architecture of cognitive control within the cerebral cortex in schizophrenia.” 2011. Doctoral Dissertation, Aix-Marseille 1. Accessed April 21, 2019. http://www.theses.fr/2011AIX10021.

MLA Handbook (7th Edition):

Pacull, Julien. “Modèle numérique micro-mécanique d'agrégat polycristallin pour le comportement des combustibles oxydes : Architecture of cognitive control within the cerebral cortex in schizophrenia.” 2011. Web. 21 Apr 2019.

Vancouver:

Pacull J. Modèle numérique micro-mécanique d'agrégat polycristallin pour le comportement des combustibles oxydes : Architecture of cognitive control within the cerebral cortex in schizophrenia. [Internet] [Doctoral dissertation]. Aix-Marseille 1; 2011. [cited 2019 Apr 21]. Available from: http://www.theses.fr/2011AIX10021.

Council of Science Editors:

Pacull J. Modèle numérique micro-mécanique d'agrégat polycristallin pour le comportement des combustibles oxydes : Architecture of cognitive control within the cerebral cortex in schizophrenia. [Doctoral Dissertation]. Aix-Marseille 1; 2011. Available from: http://www.theses.fr/2011AIX10021


McMaster University

5. Kugler, Gerhard. Ternary Fission Studies of 235U.

Degree: PhD, 1970, McMaster University

Part I describes experiments carried out to search for possible products of ternary fission of 235U. Inert gases extracted from neutron-irradiated 235u were analyzed… (more)

Subjects/Keywords: ternary; fission; inert gases; radioactive; nuclides

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APA (6th Edition):

Kugler, G. (1970). Ternary Fission Studies of 235U. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/18328

Chicago Manual of Style (16th Edition):

Kugler, Gerhard. “Ternary Fission Studies of 235U.” 1970. Doctoral Dissertation, McMaster University. Accessed April 21, 2019. http://hdl.handle.net/11375/18328.

MLA Handbook (7th Edition):

Kugler, Gerhard. “Ternary Fission Studies of 235U.” 1970. Web. 21 Apr 2019.

Vancouver:

Kugler G. Ternary Fission Studies of 235U. [Internet] [Doctoral dissertation]. McMaster University; 1970. [cited 2019 Apr 21]. Available from: http://hdl.handle.net/11375/18328.

Council of Science Editors:

Kugler G. Ternary Fission Studies of 235U. [Doctoral Dissertation]. McMaster University; 1970. Available from: http://hdl.handle.net/11375/18328

6. Shi, Lei. Etude par calcul de structure électronique des dioxydes d'uranium et de cérium contenant des défauts et des impuretés : Theoretical study using electronic structure calculations of uranium and cerium dioxides containing defects and impurities.

Degree: Docteur es, Matière condensée et nanosciences, 2016, Aix Marseille Université

Le dioxyde d'uranium (UO2) est le combustible nucléaire le plus largement utilisé dans les réacteurs nucléaires à travers le monde. En conditions d’exploitation, UO2 est… (more)

Subjects/Keywords: Calcul de structure électronique; Dioxyde d'uranium; Dioxyde de cérium; Défauts ponctuels; Gaz de fission; Dft+u; Electronic structure calculationss; Uranium dioxide; Cerium dioxide; Point defects; Fission gases; Dft+u

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APA (6th Edition):

Shi, L. (2016). Etude par calcul de structure électronique des dioxydes d'uranium et de cérium contenant des défauts et des impuretés : Theoretical study using electronic structure calculations of uranium and cerium dioxides containing defects and impurities. (Doctoral Dissertation). Aix Marseille Université. Retrieved from http://www.theses.fr/2016AIXM4345

Chicago Manual of Style (16th Edition):

Shi, Lei. “Etude par calcul de structure électronique des dioxydes d'uranium et de cérium contenant des défauts et des impuretés : Theoretical study using electronic structure calculations of uranium and cerium dioxides containing defects and impurities.” 2016. Doctoral Dissertation, Aix Marseille Université. Accessed April 21, 2019. http://www.theses.fr/2016AIXM4345.

MLA Handbook (7th Edition):

Shi, Lei. “Etude par calcul de structure électronique des dioxydes d'uranium et de cérium contenant des défauts et des impuretés : Theoretical study using electronic structure calculations of uranium and cerium dioxides containing defects and impurities.” 2016. Web. 21 Apr 2019.

Vancouver:

Shi L. Etude par calcul de structure électronique des dioxydes d'uranium et de cérium contenant des défauts et des impuretés : Theoretical study using electronic structure calculations of uranium and cerium dioxides containing defects and impurities. [Internet] [Doctoral dissertation]. Aix Marseille Université 2016. [cited 2019 Apr 21]. Available from: http://www.theses.fr/2016AIXM4345.

Council of Science Editors:

Shi L. Etude par calcul de structure électronique des dioxydes d'uranium et de cérium contenant des défauts et des impuretés : Theoretical study using electronic structure calculations of uranium and cerium dioxides containing defects and impurities. [Doctoral Dissertation]. Aix Marseille Université 2016. Available from: http://www.theses.fr/2016AIXM4345

7. Skorek, Richard. Étude par Dynamique d’Amas de l’influence des défauts d’irradiation sur la migration des gaz de fission dans le dioxyde d’uranium : A Cluster Dynamics study of fission gases in uranium dioxide.

Degree: Docteur es, Matière condensée et Nanosciences, 2013, Aix Marseille Université

Le dioxyde d'uranium UO2 est le combustible nucléaire standard des réacteurs à eau pressurisée. Durant le fonctionnement du réacteur, la fission de l'uranium produit une… (more)

Subjects/Keywords: Combustible nucléaire; UO2; Défauts; Gaz de fission; Dynamique d'amas; TDS; Nuclear Fuel; Defects; UO2; Fissions gases; Cluster Dynamics; TDS

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APA (6th Edition):

Skorek, R. (2013). Étude par Dynamique d’Amas de l’influence des défauts d’irradiation sur la migration des gaz de fission dans le dioxyde d’uranium : A Cluster Dynamics study of fission gases in uranium dioxide. (Doctoral Dissertation). Aix Marseille Université. Retrieved from http://www.theses.fr/2013AIXM4376

Chicago Manual of Style (16th Edition):

Skorek, Richard. “Étude par Dynamique d’Amas de l’influence des défauts d’irradiation sur la migration des gaz de fission dans le dioxyde d’uranium : A Cluster Dynamics study of fission gases in uranium dioxide.” 2013. Doctoral Dissertation, Aix Marseille Université. Accessed April 21, 2019. http://www.theses.fr/2013AIXM4376.

MLA Handbook (7th Edition):

Skorek, Richard. “Étude par Dynamique d’Amas de l’influence des défauts d’irradiation sur la migration des gaz de fission dans le dioxyde d’uranium : A Cluster Dynamics study of fission gases in uranium dioxide.” 2013. Web. 21 Apr 2019.

Vancouver:

Skorek R. Étude par Dynamique d’Amas de l’influence des défauts d’irradiation sur la migration des gaz de fission dans le dioxyde d’uranium : A Cluster Dynamics study of fission gases in uranium dioxide. [Internet] [Doctoral dissertation]. Aix Marseille Université 2013. [cited 2019 Apr 21]. Available from: http://www.theses.fr/2013AIXM4376.

Council of Science Editors:

Skorek R. Étude par Dynamique d’Amas de l’influence des défauts d’irradiation sur la migration des gaz de fission dans le dioxyde d’uranium : A Cluster Dynamics study of fission gases in uranium dioxide. [Doctoral Dissertation]. Aix Marseille Université 2013. Available from: http://www.theses.fr/2013AIXM4376

8. Gibson, Hubert C. Gaseous swelling and release in nuclear fuels during grain growth.

Degree: MS, Mechanical Engineering, 2013, Georgia Tech

 A model of the generation and release of fission gas, as well as the total swelling over time, was created. It uses an ideal spherical… (more)

Subjects/Keywords: Nuclear fuel; Gaseous swelling; Gas release; Fission gases; Nuclear fuels; Gases, Rare

…Krypton, Xenon, Argon, and other noble gases. At temperatures above 1300 K, gaseous fission… …Intragranular Bubbles are not shown. These fission gases are of intense interest in research, due to… …these intergranular gases cause exceeds that of solid fission products. The swelling is large… …the fuel. Fission gases tend to be highly radioactive and are able to migrate to the… …grain size can relocate the fission gases much more quickly than diffusion, so the diffusion… 

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APA (6th Edition):

Gibson, H. C. (2013). Gaseous swelling and release in nuclear fuels during grain growth. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/49103

Chicago Manual of Style (16th Edition):

Gibson, Hubert C. “Gaseous swelling and release in nuclear fuels during grain growth.” 2013. Masters Thesis, Georgia Tech. Accessed April 21, 2019. http://hdl.handle.net/1853/49103.

MLA Handbook (7th Edition):

Gibson, Hubert C. “Gaseous swelling and release in nuclear fuels during grain growth.” 2013. Web. 21 Apr 2019.

Vancouver:

Gibson HC. Gaseous swelling and release in nuclear fuels during grain growth. [Internet] [Masters thesis]. Georgia Tech; 2013. [cited 2019 Apr 21]. Available from: http://hdl.handle.net/1853/49103.

Council of Science Editors:

Gibson HC. Gaseous swelling and release in nuclear fuels during grain growth. [Masters Thesis]. Georgia Tech; 2013. Available from: http://hdl.handle.net/1853/49103

9. Beeler, Benjamin Warren. Atomistic investigations of uranium.

Degree: PhD, Mechanical Engineering, 2013, Georgia Tech

 Uranium (U) exhibits a high temperature body-centered cubic (bcc) allotrope that is often stabilized by alloying with transition metals such as Zr, Mo, and Nb… (more)

Subjects/Keywords: Uranium; Alloys; Modified embedded-atom method; Nuclear fuels; Uranium as fuel; Fission gases; Nuclear fuels Breeding

fission conditions, creating fission product gases such as helium, xenon and krypton. Several… …fission product gases in the fuel matrix during burnup. The specific isotopic yields for fission… …gases present in the fission environment are helium, xenon and krypton. Research efforts [… …interstitial. The reference state for the fission gases was assumed to be an equilibrium facecentered… …agreement with experiment. Calculations of dilute fission gas defects show reasonable agreement… 

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APA (6th Edition):

Beeler, B. W. (2013). Atomistic investigations of uranium. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/49055

Chicago Manual of Style (16th Edition):

Beeler, Benjamin Warren. “Atomistic investigations of uranium.” 2013. Doctoral Dissertation, Georgia Tech. Accessed April 21, 2019. http://hdl.handle.net/1853/49055.

MLA Handbook (7th Edition):

Beeler, Benjamin Warren. “Atomistic investigations of uranium.” 2013. Web. 21 Apr 2019.

Vancouver:

Beeler BW. Atomistic investigations of uranium. [Internet] [Doctoral dissertation]. Georgia Tech; 2013. [cited 2019 Apr 21]. Available from: http://hdl.handle.net/1853/49055.

Council of Science Editors:

Beeler BW. Atomistic investigations of uranium. [Doctoral Dissertation]. Georgia Tech; 2013. Available from: http://hdl.handle.net/1853/49055

10. Beeler, Benjamin Warren. Atomistic simulations of intrinsic and extrinsic point defects in uranium.

Degree: MS, Mechanical Engineering, 2011, Georgia Tech

 Uranium (U) exhibits a high temperature body-centered cubic (b.c.c.) allotrope that is often stabilized by alloying with transition metals such as Zr, Mo, and Nb… (more)

Subjects/Keywords: Fission gases; Point defects; First principles; Uranium; Uranium Defects; Computer simulation; Deformations (Mechanics)

fission product gases in the fuel matrix during burnup. The specific isotopic yields for fission… …gases present in the fission environment are helium, xenon and krypton. Research efforts [… …of a lattice containing one Zr interstitial. The reference state for the fission gases was… …seems appropriate for fission gases based on the energies of these respective defect… …comparing the formation energies of fission gases to the self-defects, the Xe and Kr defects are… 

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APA (6th Edition):

Beeler, B. W. (2011). Atomistic simulations of intrinsic and extrinsic point defects in uranium. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/42833

Chicago Manual of Style (16th Edition):

Beeler, Benjamin Warren. “Atomistic simulations of intrinsic and extrinsic point defects in uranium.” 2011. Masters Thesis, Georgia Tech. Accessed April 21, 2019. http://hdl.handle.net/1853/42833.

MLA Handbook (7th Edition):

Beeler, Benjamin Warren. “Atomistic simulations of intrinsic and extrinsic point defects in uranium.” 2011. Web. 21 Apr 2019.

Vancouver:

Beeler BW. Atomistic simulations of intrinsic and extrinsic point defects in uranium. [Internet] [Masters thesis]. Georgia Tech; 2011. [cited 2019 Apr 21]. Available from: http://hdl.handle.net/1853/42833.

Council of Science Editors:

Beeler BW. Atomistic simulations of intrinsic and extrinsic point defects in uranium. [Masters Thesis]. Georgia Tech; 2011. Available from: http://hdl.handle.net/1853/42833

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