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You searched for subject:(Generation IV nuclear reactor). Showing records 1 – 30 of 26264 total matches.

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University of Ontario Institute of Technology

1. Thind, Harwinder. Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP.

Degree: 2012, University of Ontario Institute of Technology

 SuperCritical-Water-cooled Reactors (SCWRs) are being developed as one of the Generation-IV nuclear-reactor concepts. SuperCritical Water (SCW) Nuclear Power Plants (NPPs) are expected to have much… (more)

Subjects/Keywords: Generation IV reactor; SuperCritical water-cooled nuclear reactor; Thermodynamic cycle; Heat exchanger

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APA (6th Edition):

Thind, H. (2012). Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/227

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):

Thind, Harwinder. “Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP.” 2012. Thesis, University of Ontario Institute of Technology. Accessed June 16, 2019. http://hdl.handle.net/10155/227.

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

MLA Handbook (7th Edition):

Thind, Harwinder. “Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP.” 2012. Web. 16 Jun 2019.

Vancouver:

Thind H. Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP. [Internet] [Thesis]. University of Ontario Institute of Technology; 2012. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/10155/227.

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

Council of Science Editors:

Thind H. Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP. [Thesis]. University of Ontario Institute of Technology; 2012. Available from: http://hdl.handle.net/10155/227

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


University of Illinois – Urbana-Champaign

2. Yan, Yizhou. Development of a coupled CFD???system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors.

Degree: PhD, Nuclear Engineering, 2012, University of Illinois – Urbana-Champaign

 Motivated by recent developments in the field of Computational Fluid Dynamics (CFD) and recognizing the limitations on computing power, this dissertation is aimed at combining… (more)

Subjects/Keywords: GEN IV Nuclear Reactor; Thermal Hydraulic; Computational Fluid Dynamics (CFD); RELAP; Coupled Simulation; Porous Media Model; Generation IV (GEN IV)

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APA (6th Edition):

Yan, Y. (2012). Development of a coupled CFD???system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors. (Doctoral Dissertation). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/29660

Chicago Manual of Style (16th Edition):

Yan, Yizhou. “Development of a coupled CFD???system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors.” 2012. Doctoral Dissertation, University of Illinois – Urbana-Champaign. Accessed June 16, 2019. http://hdl.handle.net/2142/29660.

MLA Handbook (7th Edition):

Yan, Yizhou. “Development of a coupled CFD???system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors.” 2012. Web. 16 Jun 2019.

Vancouver:

Yan Y. Development of a coupled CFD???system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors. [Internet] [Doctoral dissertation]. University of Illinois – Urbana-Champaign; 2012. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/2142/29660.

Council of Science Editors:

Yan Y. Development of a coupled CFD???system-code capability (with a modified porous media model) and its applications to simulate current and next generation reactors. [Doctoral Dissertation]. University of Illinois – Urbana-Champaign; 2012. Available from: http://hdl.handle.net/2142/29660


Penn State University

3. Kunkle, Jamie McKinney. STRUCTURE OF OXIDE LAYERS FORMED ON CANDIDATE STEEL ALLOYS EXPOSED TO FLOWING LEAD-BISMUTH EUTECTIC FOR GENERATION IV REACTOR APPLICATIONS.

Degree: MS, Nuclear Engineering, 2009, Penn State University

 Ferritic-martensitic steels of interest for use in Generation IV lead cooled fast reactors were corroded in a flowing lead-bismuth eutectic environment and the microstructures of… (more)

Subjects/Keywords: lead-bismuth eutectic; corrosion; Generation IV Nuclear Reactors; lead cooled fast reactor

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APA (6th Edition):

Kunkle, J. M. (2009). STRUCTURE OF OXIDE LAYERS FORMED ON CANDIDATE STEEL ALLOYS EXPOSED TO FLOWING LEAD-BISMUTH EUTECTIC FOR GENERATION IV REACTOR APPLICATIONS. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/9122

Chicago Manual of Style (16th Edition):

Kunkle, Jamie McKinney. “STRUCTURE OF OXIDE LAYERS FORMED ON CANDIDATE STEEL ALLOYS EXPOSED TO FLOWING LEAD-BISMUTH EUTECTIC FOR GENERATION IV REACTOR APPLICATIONS.” 2009. Masters Thesis, Penn State University. Accessed June 16, 2019. https://etda.libraries.psu.edu/catalog/9122.

MLA Handbook (7th Edition):

Kunkle, Jamie McKinney. “STRUCTURE OF OXIDE LAYERS FORMED ON CANDIDATE STEEL ALLOYS EXPOSED TO FLOWING LEAD-BISMUTH EUTECTIC FOR GENERATION IV REACTOR APPLICATIONS.” 2009. Web. 16 Jun 2019.

Vancouver:

Kunkle JM. STRUCTURE OF OXIDE LAYERS FORMED ON CANDIDATE STEEL ALLOYS EXPOSED TO FLOWING LEAD-BISMUTH EUTECTIC FOR GENERATION IV REACTOR APPLICATIONS. [Internet] [Masters thesis]. Penn State University; 2009. [cited 2019 Jun 16]. Available from: https://etda.libraries.psu.edu/catalog/9122.

Council of Science Editors:

Kunkle JM. STRUCTURE OF OXIDE LAYERS FORMED ON CANDIDATE STEEL ALLOYS EXPOSED TO FLOWING LEAD-BISMUTH EUTECTIC FOR GENERATION IV REACTOR APPLICATIONS. [Masters Thesis]. Penn State University; 2009. Available from: https://etda.libraries.psu.edu/catalog/9122


University of California – Berkeley

4. Heidet, Florent. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation.

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

 The primary objective of this study was to estimate the maximum fuel utilization that is achievable using fast reactors that are designed to operate with… (more)

Subjects/Keywords: Nuclear Engineering; Breed and burn; Burnup; Fast reactor; Fuel cycle; Generation IV; Uranium utilization

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APA (6th Edition):

Heidet, F. (2010). Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/63j4k05n

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):

Heidet, Florent. “Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation.” 2010. Thesis, University of California – Berkeley. Accessed June 16, 2019. http://www.escholarship.org/uc/item/63j4k05n.

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

MLA Handbook (7th Edition):

Heidet, Florent. “Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation.” 2010. Web. 16 Jun 2019.

Vancouver:

Heidet F. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation. [Internet] [Thesis]. University of California – Berkeley; 2010. [cited 2019 Jun 16]. Available from: http://www.escholarship.org/uc/item/63j4k05n.

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

Council of Science Editors:

Heidet F. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation. [Thesis]. University of California – Berkeley; 2010. Available from: http://www.escholarship.org/uc/item/63j4k05n

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


Brno University of Technology

5. Slančík, Tomáš. Výzkum a vývoj jaderných reaktorů IV. generace s důrazem na reaktory s tekutými solemi .

Degree: 2017, Brno University of Technology

 Bakalárska práca sa zaoberá vytvorením prehľadu jednotlivých generácii jadrových reaktorov od prvých prototypov až po dnešné pokročilé reaktory. Tiež prináša prehľad o projektoch podporujúcich rozvoj… (more)

Subjects/Keywords: Jadrový reaktor; IV. generácia; medzinárodné projekty; reaktory s tekutými soľami; Nuclear reactor; generation IV; international projects; molten salt reactors

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APA (6th Edition):

Slančík, T. (2017). Výzkum a vývoj jaderných reaktorů IV. generace s důrazem na reaktory s tekutými solemi . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/68103

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):

Slančík, Tomáš. “Výzkum a vývoj jaderných reaktorů IV. generace s důrazem na reaktory s tekutými solemi .” 2017. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/68103.

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

MLA Handbook (7th Edition):

Slančík, Tomáš. “Výzkum a vývoj jaderných reaktorů IV. generace s důrazem na reaktory s tekutými solemi .” 2017. Web. 16 Jun 2019.

Vancouver:

Slančík T. Výzkum a vývoj jaderných reaktorů IV. generace s důrazem na reaktory s tekutými solemi . [Internet] [Thesis]. Brno University of Technology; 2017. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/68103.

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

Council of Science Editors:

Slančík T. Výzkum a vývoj jaderných reaktorů IV. generace s důrazem na reaktory s tekutými solemi . [Thesis]. Brno University of Technology; 2017. Available from: http://hdl.handle.net/11012/68103

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


University of Ontario Institute of Technology

6. Lukomski, Andrew John. Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility.

Degree: 2011, University of Ontario Institute of Technology

 The SuperCritical Water-cooled nuclear Reactor (SCWR) is one of six Generation-IV nuclear-reactor concepts currently being designed. It will operate at pressures of 25 MPa and… (more)

Subjects/Keywords: Hydrogen production; Thermochemical cycles; Copper-chlorine cycle; Generation IV reactor; SuperCritical water-cooled nuclear reactor; Heat exchanger

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APA (6th Edition):

Lukomski, A. J. (2011). Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/179

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):

Lukomski, Andrew John. “Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility.” 2011. Thesis, University of Ontario Institute of Technology. Accessed June 16, 2019. http://hdl.handle.net/10155/179.

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

MLA Handbook (7th Edition):

Lukomski, Andrew John. “Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility.” 2011. Web. 16 Jun 2019.

Vancouver:

Lukomski AJ. Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility. [Internet] [Thesis]. University of Ontario Institute of Technology; 2011. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/10155/179.

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

Council of Science Editors:

Lukomski AJ. Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility. [Thesis]. University of Ontario Institute of Technology; 2011. Available from: http://hdl.handle.net/10155/179

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


Uppsala University

7. Lindell, Matilda Åberg. Safeguards Licensing Aspects of a Future Generation IV Demonstration Facility : A Case Study.

Degree: Applied Nuclear Physics, 2010, Uppsala University

Generation IV (Gen IV) is a developing new generation of nuclear power reactors which is foreseen to bring about a safer and more sustainable… (more)

Subjects/Keywords: safeguards; Generation IV; lead-cooled fast reactor

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APA (6th Edition):

Lindell, M. . (2010). Safeguards Licensing Aspects of a Future Generation IV Demonstration Facility : A Case Study. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-129232

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):

Lindell, Matilda Åberg. “Safeguards Licensing Aspects of a Future Generation IV Demonstration Facility : A Case Study.” 2010. Thesis, Uppsala University. Accessed June 16, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-129232.

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

MLA Handbook (7th Edition):

Lindell, Matilda Åberg. “Safeguards Licensing Aspects of a Future Generation IV Demonstration Facility : A Case Study.” 2010. Web. 16 Jun 2019.

Vancouver:

Lindell M. Safeguards Licensing Aspects of a Future Generation IV Demonstration Facility : A Case Study. [Internet] [Thesis]. Uppsala University; 2010. [cited 2019 Jun 16]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-129232.

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

Council of Science Editors:

Lindell M. Safeguards Licensing Aspects of a Future Generation IV Demonstration Facility : A Case Study. [Thesis]. Uppsala University; 2010. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-129232

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


Uppsala University

8. Hareland, Mathias. CONQUER CORROSION : Key issues of the lead-cooled fast reactor design.

Degree: Applied Nuclear Physics, 2011, Uppsala University

  The lead-cooled fast reactor (LFR) is one of the concepts of the Generation IV reactorsystems. There are some issues that have to be solved… (more)

Subjects/Keywords: Nuclear power; Generation-IV; lead cooled fast reactor; LFR; corrosion; MAXTHAL; MYRRHA; Lead-bismuth eutectic; LBE

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APA (6th Edition):

Hareland, M. (2011). CONQUER CORROSION : Key issues of the lead-cooled fast reactor design. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-149755

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):

Hareland, Mathias. “CONQUER CORROSION : Key issues of the lead-cooled fast reactor design.” 2011. Thesis, Uppsala University. Accessed June 16, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-149755.

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

MLA Handbook (7th Edition):

Hareland, Mathias. “CONQUER CORROSION : Key issues of the lead-cooled fast reactor design.” 2011. Web. 16 Jun 2019.

Vancouver:

Hareland M. CONQUER CORROSION : Key issues of the lead-cooled fast reactor design. [Internet] [Thesis]. Uppsala University; 2011. [cited 2019 Jun 16]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-149755.

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

Council of Science Editors:

Hareland M. CONQUER CORROSION : Key issues of the lead-cooled fast reactor design. [Thesis]. Uppsala University; 2011. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-149755

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


Brno University of Technology

9. Kostečka, Jan. Studium chování jaderného reaktoru chlazeného tekutými solemi .

Degree: 2018, Brno University of Technology

 Diplomová práce se zaobírá studiem chování jaderných reaktorů chlazenými tekutými solemi a aplikací tekutých solí pro IV. Generaci jaderných reaktorů. Pro použití tekuté soli je… (more)

Subjects/Keywords: Roztavené soli; IV. Generace jaderných reaktorů; MSR; fluoridový soli; chloridový soli.; Molten salt; IV. Generation of a nuclear reactor; MSR; fluoride’s salt; chloride’s salt.

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APA (6th Edition):

Kostečka, J. (2018). Studium chování jaderného reaktoru chlazeného tekutými solemi . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/80732

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):

Kostečka, Jan. “Studium chování jaderného reaktoru chlazeného tekutými solemi .” 2018. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/80732.

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

MLA Handbook (7th Edition):

Kostečka, Jan. “Studium chování jaderného reaktoru chlazeného tekutými solemi .” 2018. Web. 16 Jun 2019.

Vancouver:

Kostečka J. Studium chování jaderného reaktoru chlazeného tekutými solemi . [Internet] [Thesis]. Brno University of Technology; 2018. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/80732.

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

Council of Science Editors:

Kostečka J. Studium chování jaderného reaktoru chlazeného tekutými solemi . [Thesis]. Brno University of Technology; 2018. Available from: http://hdl.handle.net/11012/80732

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


Brno University of Technology

10. Hovorka, Martin. Materiály pro reaktory IV. generace .

Degree: 2014, Brno University of Technology

 Cílem této práce je popis vybraných reaktorů IV. generace – VHTR, SCWR a MSR z hlediska jejich materiálových požadavků s důrazem na reaktor VHTR. V… (more)

Subjects/Keywords: Jaderný; reaktor; IV. generace; VHTR; materiál; SCWR; MSR; jaderná elektrárna; Monel; Inconel; Hastelloy; Nuclear; reactor; IV generation; VHTR; material; SCWR; MSR; power plant; Monel; Inconel. Hastelloy

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

APA (6th Edition):

Hovorka, M. (2014). Materiály pro reaktory IV. generace . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/32439

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):

Hovorka, Martin. “Materiály pro reaktory IV. generace .” 2014. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/32439.

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

MLA Handbook (7th Edition):

Hovorka, Martin. “Materiály pro reaktory IV. generace .” 2014. Web. 16 Jun 2019.

Vancouver:

Hovorka M. Materiály pro reaktory IV. generace . [Internet] [Thesis]. Brno University of Technology; 2014. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/32439.

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

Council of Science Editors:

Hovorka M. Materiály pro reaktory IV. generace . [Thesis]. Brno University of Technology; 2014. Available from: http://hdl.handle.net/11012/32439

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


Delft University of Technology

11. Van Gendt, G.J. Closing the nuclear fuel cycle: potential of the gas cooled fast reactor:.

Degree: Applied Sciences, Geo-Database Management Center, 2007, Delft University of Technology

 The fuel composition of the Generation IV 600 MWth 'efficient' Gas Cooled Fast Reactor (GCFR) that realizes zero breeding gain without using fertile blankets is… (more)

Subjects/Keywords: gas cooled fast reactor; generation iv; nuclear reactor; minor actinides; decay heat production

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APA (6th Edition):

Van Gendt, G. J. (2007). Closing the nuclear fuel cycle: potential of the gas cooled fast reactor:. (Masters Thesis). Delft University of Technology. Retrieved from http://resolver.tudelft.nl/uuid:bdbef4b7-fb90-4991-9ef8-b4b6a17fca4f

Chicago Manual of Style (16th Edition):

Van Gendt, G J. “Closing the nuclear fuel cycle: potential of the gas cooled fast reactor:.” 2007. Masters Thesis, Delft University of Technology. Accessed June 16, 2019. http://resolver.tudelft.nl/uuid:bdbef4b7-fb90-4991-9ef8-b4b6a17fca4f.

MLA Handbook (7th Edition):

Van Gendt, G J. “Closing the nuclear fuel cycle: potential of the gas cooled fast reactor:.” 2007. Web. 16 Jun 2019.

Vancouver:

Van Gendt GJ. Closing the nuclear fuel cycle: potential of the gas cooled fast reactor:. [Internet] [Masters thesis]. Delft University of Technology; 2007. [cited 2019 Jun 16]. Available from: http://resolver.tudelft.nl/uuid:bdbef4b7-fb90-4991-9ef8-b4b6a17fca4f.

Council of Science Editors:

Van Gendt GJ. Closing the nuclear fuel cycle: potential of the gas cooled fast reactor:. [Masters Thesis]. Delft University of Technology; 2007. Available from: http://resolver.tudelft.nl/uuid:bdbef4b7-fb90-4991-9ef8-b4b6a17fca4f


McMaster University

12. Moghrabi, Ahmad. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.

Degree: PhD, 2018, McMaster University

The Generation IV International Forum (GIF) has initiated an international collaboration for the research and development of the Generation IV future nuclear energy systems. The… (more)

Subjects/Keywords: Generation IV nuclear reactor; Canadian PT-SCWR; Advanced nuclear Energy system; Lattice physics phenomena; Energy group structure optimization; SCALE code; Uncertainty Analysis; Sensitivity Analysis; Transport Calcuations; Optimization and algorithm

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APA (6th Edition):

Moghrabi, A. (2018). INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. (Doctoral Dissertation). McMaster University. Retrieved from http://hdl.handle.net/11375/22886

Chicago Manual of Style (16th Edition):

Moghrabi, Ahmad. “INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.” 2018. Doctoral Dissertation, McMaster University. Accessed June 16, 2019. http://hdl.handle.net/11375/22886.

MLA Handbook (7th Edition):

Moghrabi, Ahmad. “INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR.” 2018. Web. 16 Jun 2019.

Vancouver:

Moghrabi A. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. [Internet] [Doctoral dissertation]. McMaster University; 2018. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11375/22886.

Council of Science Editors:

Moghrabi A. INVESTIGATION OF LATTICE PHYSICS PHENOMENA WITH UNCERTAINTY ANALYSIS AND SENSITIVITY STUDY OF ENERGY GROUP DISCRETIZATION FOR THE CANADIAN PRESSURE TUBE SUPERCRITICAL WATER-COOLED REACTOR. [Doctoral Dissertation]. McMaster University; 2018. Available from: http://hdl.handle.net/11375/22886


University of Ontario Institute of Technology

13. Peiman, Wargha. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs).

Degree: 2017, University of Ontario Institute of Technology

 A group of countries has initiated an international collaboration to develop a next generation (i.e., Generation IV) of nuclear reactors. Chosen as one of the… (more)

Subjects/Keywords: SCWR; Thermalhydraulics; Neutronics; Generation IV; Nuclear fuel

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APA (6th Edition):

Peiman, W. (2017). Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs). (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/827

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):

Peiman, Wargha. “Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs).” 2017. Thesis, University of Ontario Institute of Technology. Accessed June 16, 2019. http://hdl.handle.net/10155/827.

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

MLA Handbook (7th Edition):

Peiman, Wargha. “Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs).” 2017. Web. 16 Jun 2019.

Vancouver:

Peiman W. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs). [Internet] [Thesis]. University of Ontario Institute of Technology; 2017. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/10155/827.

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

Council of Science Editors:

Peiman W. Study on specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs). [Thesis]. University of Ontario Institute of Technology; 2017. Available from: http://hdl.handle.net/10155/827

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


Uppsala University

14. Sivertsson, Viktor. Hydrogen production using high temperature nuclear reactors : A feasibility study.

Degree: Applied Nuclear Physics, 2010, Uppsala University

  The use of hydrogen is predicted to increase substantially in the future, both as chemical feedstock and also as energy carrier for transportation. The… (more)

Subjects/Keywords: HTGR; HTR; VHTR; Hydrogen; Nuclear power; Generation IV; Generation 4; Gen IV; Gen 4

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APA (6th Edition):

Sivertsson, V. (2010). Hydrogen production using high temperature nuclear reactors : A feasibility study. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-120742

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):

Sivertsson, Viktor. “Hydrogen production using high temperature nuclear reactors : A feasibility study.” 2010. Thesis, Uppsala University. Accessed June 16, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-120742.

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

MLA Handbook (7th Edition):

Sivertsson, Viktor. “Hydrogen production using high temperature nuclear reactors : A feasibility study.” 2010. Web. 16 Jun 2019.

Vancouver:

Sivertsson V. Hydrogen production using high temperature nuclear reactors : A feasibility study. [Internet] [Thesis]. Uppsala University; 2010. [cited 2019 Jun 16]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-120742.

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

Council of Science Editors:

Sivertsson V. Hydrogen production using high temperature nuclear reactors : A feasibility study. [Thesis]. Uppsala University; 2010. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-120742

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


Penn State University

15. Baird, Jenna J. Scaled Experiments on Air Ingress in the Very High Temperature Reactor (VHTR).

Degree: MS, Nuclear Engineering, 2010, Penn State University

 In the postulated Depressurized Loss of Forced Convection (D-LOFC) for the Very High Temperature Reactor (VHTR), the gravity driven air ingress phenomenon is of particular… (more)

Subjects/Keywords: air ingress; generation IV reactors; very high temperature reactor; gravity driven exchange

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APA (6th Edition):

Baird, J. J. (2010). Scaled Experiments on Air Ingress in the Very High Temperature Reactor (VHTR). (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/11502

Chicago Manual of Style (16th Edition):

Baird, Jenna J. “Scaled Experiments on Air Ingress in the Very High Temperature Reactor (VHTR).” 2010. Masters Thesis, Penn State University. Accessed June 16, 2019. https://etda.libraries.psu.edu/catalog/11502.

MLA Handbook (7th Edition):

Baird, Jenna J. “Scaled Experiments on Air Ingress in the Very High Temperature Reactor (VHTR).” 2010. Web. 16 Jun 2019.

Vancouver:

Baird JJ. Scaled Experiments on Air Ingress in the Very High Temperature Reactor (VHTR). [Internet] [Masters thesis]. Penn State University; 2010. [cited 2019 Jun 16]. Available from: https://etda.libraries.psu.edu/catalog/11502.

Council of Science Editors:

Baird JJ. Scaled Experiments on Air Ingress in the Very High Temperature Reactor (VHTR). [Masters Thesis]. Penn State University; 2010. Available from: https://etda.libraries.psu.edu/catalog/11502


University of New Mexico

16. Zohuri, Bahman. INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS.

Degree: Nuclear Engineering, 2014, University of New Mexico

 The purpose of this research was to model and analyze a nuclear heated multi-turbine power conversion system operating with atmospheric air as the working fluid.… (more)

Subjects/Keywords: Brayton-Rankine combined cycle; Recuperated Brayton; generation IV nuclear power plants

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APA (6th Edition):

Zohuri, B. (2014). INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS. (Doctoral Dissertation). University of New Mexico. Retrieved from http://hdl.handle.net/1928/24364

Chicago Manual of Style (16th Edition):

Zohuri, Bahman. “INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS.” 2014. Doctoral Dissertation, University of New Mexico. Accessed June 16, 2019. http://hdl.handle.net/1928/24364.

MLA Handbook (7th Edition):

Zohuri, Bahman. “INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS.” 2014. Web. 16 Jun 2019.

Vancouver:

Zohuri B. INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS. [Internet] [Doctoral dissertation]. University of New Mexico; 2014. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/1928/24364.

Council of Science Editors:

Zohuri B. INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS. [Doctoral Dissertation]. University of New Mexico; 2014. Available from: http://hdl.handle.net/1928/24364


Georgia Tech

17. Scott, Katherine. Characterization of nuclear reactor pressure vessel (RPV) surrogate specimens with ultrasound.

Degree: MS, Mechanical Engineering, 2016, Georgia Tech

 This research determines the sensitivity of nonlinear ultrasound (NLU) to the changes in microstructure of heat treated Fe-1.0% Cu and Fe-0.1% Cu binary alloys. The… (more)

Subjects/Keywords: Nonlinear ultrasound; Second harmonic generation; Nuclear reactor pressure vessel; Surrogate specimens

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APA (6th Edition):

Scott, K. (2016). Characterization of nuclear reactor pressure vessel (RPV) surrogate specimens with ultrasound. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/56363

Chicago Manual of Style (16th Edition):

Scott, Katherine. “Characterization of nuclear reactor pressure vessel (RPV) surrogate specimens with ultrasound.” 2016. Masters Thesis, Georgia Tech. Accessed June 16, 2019. http://hdl.handle.net/1853/56363.

MLA Handbook (7th Edition):

Scott, Katherine. “Characterization of nuclear reactor pressure vessel (RPV) surrogate specimens with ultrasound.” 2016. Web. 16 Jun 2019.

Vancouver:

Scott K. Characterization of nuclear reactor pressure vessel (RPV) surrogate specimens with ultrasound. [Internet] [Masters thesis]. Georgia Tech; 2016. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/1853/56363.

Council of Science Editors:

Scott K. Characterization of nuclear reactor pressure vessel (RPV) surrogate specimens with ultrasound. [Masters Thesis]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/56363


University of Missouri – Columbia

18. Maynard, Raymond K. Total hemispherical emissivity of very high temperature reactor (VHTR) candidate materials: Hastelloy X, Haynes 230, and Alloy 617.

Degree: 2011, University of Missouri – Columbia

 An experimental system was constructed in accordance with the standard ASTM C835-06 to measure the total hemispherical emissivity of structural materials of interest in Very… (more)

Subjects/Keywords: next generation nuclear reactor; very high temperature reactors; energy production; emissivity

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APA (6th Edition):

Maynard, R. K. (2011). Total hemispherical emissivity of very high temperature reactor (VHTR) candidate materials: Hastelloy X, Haynes 230, and Alloy 617. (Thesis). University of Missouri – Columbia. Retrieved from http://hdl.handle.net/10355/14216

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):

Maynard, Raymond K. “Total hemispherical emissivity of very high temperature reactor (VHTR) candidate materials: Hastelloy X, Haynes 230, and Alloy 617.” 2011. Thesis, University of Missouri – Columbia. Accessed June 16, 2019. http://hdl.handle.net/10355/14216.

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

MLA Handbook (7th Edition):

Maynard, Raymond K. “Total hemispherical emissivity of very high temperature reactor (VHTR) candidate materials: Hastelloy X, Haynes 230, and Alloy 617.” 2011. Web. 16 Jun 2019.

Vancouver:

Maynard RK. Total hemispherical emissivity of very high temperature reactor (VHTR) candidate materials: Hastelloy X, Haynes 230, and Alloy 617. [Internet] [Thesis]. University of Missouri – Columbia; 2011. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/10355/14216.

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

Council of Science Editors:

Maynard RK. Total hemispherical emissivity of very high temperature reactor (VHTR) candidate materials: Hastelloy X, Haynes 230, and Alloy 617. [Thesis]. University of Missouri – Columbia; 2011. Available from: http://hdl.handle.net/10355/14216

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


EPFL

19. Petkevich, Petr. Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor.

Degree: 2008, EPFL

 Until about the year 2030, current-day nuclear power plants (NPPs) will be replaced by so-called Gen-III or Gen-III+ units, which are mainly based on light… (more)

Subjects/Keywords: nuclear power plants; Generation-IV; gas-cooled fast reactor; GFR; plate-type fuel; thermo-mechanics; thermal-hydraulics; FAST code system; transient analysis; TRACE; fuel modeling; centrales nucléaires; Génération IV; réacteur à neutrons rapides refroidi au gaz; RNR-G; combustible à plaques; thermo-mécanique; thermo-hydraulique; système de codes FAST; analyse des transitoires; TRACE; modélisation du combustible

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APA (6th Edition):

Petkevich, P. (2008). Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor. (Thesis). EPFL. Retrieved from http://infoscience.epfl.ch/record/125884

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):

Petkevich, Petr. “Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor.” 2008. Thesis, EPFL. Accessed June 16, 2019. http://infoscience.epfl.ch/record/125884.

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

MLA Handbook (7th Edition):

Petkevich, Petr. “Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor.” 2008. Web. 16 Jun 2019.

Vancouver:

Petkevich P. Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor. [Internet] [Thesis]. EPFL; 2008. [cited 2019 Jun 16]. Available from: http://infoscience.epfl.ch/record/125884.

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

Council of Science Editors:

Petkevich P. Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor. [Thesis]. EPFL; 2008. Available from: http://infoscience.epfl.ch/record/125884

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


University of Cambridge

20. Kasam, Alisha. Conceptual design of a breed & burn molten salt reactor.

Degree: PhD, 2019, University of Cambridge

 A breed-and-burn molten salt reactor (BBMSR) concept is proposed to address the Generation IV fuel cycle sustainability objective in a once-through cycle with low enrichment… (more)

Subjects/Keywords: nuclear; molten salt; mixed convection; computational fluid dynamics; breed & burn; fast reactors; fuel cycle; Generation IV; neutronic; thermal-hydraulic; power density; uranium utilisation; breeding; natural uranium; low-enriched; fluoride salt; chloride salt; Serpent; WIMS; sodium fast reactor; fast spectrum; heat transfer correlation; finite-difference model; Monte Carlo; OpenFOAM; molten salt reactor; MATLAB

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APA (6th Edition):

Kasam, A. (2019). Conceptual design of a breed & burn molten salt reactor. (Doctoral Dissertation). University of Cambridge. Retrieved from https://www.repository.cam.ac.uk/handle/1810/289755 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.767930

Chicago Manual of Style (16th Edition):

Kasam, Alisha. “Conceptual design of a breed & burn molten salt reactor.” 2019. Doctoral Dissertation, University of Cambridge. Accessed June 16, 2019. https://www.repository.cam.ac.uk/handle/1810/289755 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.767930.

MLA Handbook (7th Edition):

Kasam, Alisha. “Conceptual design of a breed & burn molten salt reactor.” 2019. Web. 16 Jun 2019.

Vancouver:

Kasam A. Conceptual design of a breed & burn molten salt reactor. [Internet] [Doctoral dissertation]. University of Cambridge; 2019. [cited 2019 Jun 16]. Available from: https://www.repository.cam.ac.uk/handle/1810/289755 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.767930.

Council of Science Editors:

Kasam A. Conceptual design of a breed & burn molten salt reactor. [Doctoral Dissertation]. University of Cambridge; 2019. Available from: https://www.repository.cam.ac.uk/handle/1810/289755 ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.767930


University of Ontario Institute of Technology

21. Mokry, Sarah. Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications.

Degree: 2009, University of Ontario Institute of Technology

 A large set of experimental data, obtained in Russia, was analyzed and a new heat-transfer correlation for supercritical water was developed. This experimental dataset was… (more)

Subjects/Keywords: Supercritical water-cooled reactors; Supercritical water; Heat-transfer; Correlations; Generation IV nuclear reactors

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APA (6th Edition):

Mokry, S. (2009). Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/84

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):

Mokry, Sarah. “Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications.” 2009. Thesis, University of Ontario Institute of Technology. Accessed June 16, 2019. http://hdl.handle.net/10155/84.

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

MLA Handbook (7th Edition):

Mokry, Sarah. “Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications.” 2009. Web. 16 Jun 2019.

Vancouver:

Mokry S. Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications. [Internet] [Thesis]. University of Ontario Institute of Technology; 2009. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/10155/84.

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

Council of Science Editors:

Mokry S. Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications. [Thesis]. University of Ontario Institute of Technology; 2009. Available from: http://hdl.handle.net/10155/84

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


Brno University of Technology

22. Mlčúch, Adam. Jaderné reaktory 4. generace .

Degree: 2012, Brno University of Technology

 Tato bakalářská práce se zabývá vytvořením přehledu jednotlivých generací jaderných reaktorů. Největší část práce je následně věnovaná reaktorovým systémům čtvrté generace. Jednotlivé návrhy vycházejí ze… (more)

Subjects/Keywords: jaderný reaktor; čtvrtá generace; jaderná elektrárna; jaderné palivo; energetika; nuclear reactor; generation four; nuclear power plant; nuclear fuel

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APA (6th Edition):

Mlčúch, A. (2012). Jaderné reaktory 4. generace . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/10242

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):

Mlčúch, Adam. “Jaderné reaktory 4. generace .” 2012. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/10242.

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

MLA Handbook (7th Edition):

Mlčúch, Adam. “Jaderné reaktory 4. generace .” 2012. Web. 16 Jun 2019.

Vancouver:

Mlčúch A. Jaderné reaktory 4. generace . [Internet] [Thesis]. Brno University of Technology; 2012. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/10242.

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

Council of Science Editors:

Mlčúch A. Jaderné reaktory 4. generace . [Thesis]. Brno University of Technology; 2012. Available from: http://hdl.handle.net/11012/10242

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


Uppsala University

23. Lindström, Tobias. SPARC fast reactor design : Design of two passively safe metal-fuelled sodium-cooled pool-type small modular fast reactors with Autonomous Reactivity Control.

Degree: Applied Nuclear Physics, 2015, Uppsala University

  In this master thesis a small modular sodium-cooled metal-fuelled pool-type fast reactor design, called SPARC - Safe and Passive with Autonomous Reactivity control, has… (more)

Subjects/Keywords: Fast Reactor; Reactor Design; Passive; ARC; Autonomous Reactivity Control; SPARC; Safe and Passive with Autonomous Reactivity Control; Generation IV; Sodium; Pool-type; Metal-fuel; Reactivity Sustaining

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APA (6th Edition):

Lindström, T. (2015). SPARC fast reactor design : Design of two passively safe metal-fuelled sodium-cooled pool-type small modular fast reactors with Autonomous Reactivity Control. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-263506

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):

Lindström, Tobias. “SPARC fast reactor design : Design of two passively safe metal-fuelled sodium-cooled pool-type small modular fast reactors with Autonomous Reactivity Control.” 2015. Thesis, Uppsala University. Accessed June 16, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-263506.

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

MLA Handbook (7th Edition):

Lindström, Tobias. “SPARC fast reactor design : Design of two passively safe metal-fuelled sodium-cooled pool-type small modular fast reactors with Autonomous Reactivity Control.” 2015. Web. 16 Jun 2019.

Vancouver:

Lindström T. SPARC fast reactor design : Design of two passively safe metal-fuelled sodium-cooled pool-type small modular fast reactors with Autonomous Reactivity Control. [Internet] [Thesis]. Uppsala University; 2015. [cited 2019 Jun 16]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-263506.

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

Council of Science Editors:

Lindström T. SPARC fast reactor design : Design of two passively safe metal-fuelled sodium-cooled pool-type small modular fast reactors with Autonomous Reactivity Control. [Thesis]. Uppsala University; 2015. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-263506

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


University of Illinois – Chicago

24. Bersano, Andrea. Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors.

Degree: 2017, University of Illinois – Chicago

 With reference to innovative heat exchangers to be used in passive safety system of Gen- eration IV nuclear reactors and Small Modular Reactors it is… (more)

Subjects/Keywords: Generation IV nuclear reactors; passive systems; RELAP5; heat transfer in nuclear plants; Decay Heat Removal system; bayonet heat exchanger

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APA (6th Edition):

Bersano, A. (2017). Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors. (Thesis). University of Illinois – Chicago. Retrieved from http://hdl.handle.net/10027/21981

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):

Bersano, Andrea. “Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors.” 2017. Thesis, University of Illinois – Chicago. Accessed June 16, 2019. http://hdl.handle.net/10027/21981.

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

MLA Handbook (7th Edition):

Bersano, Andrea. “Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors.” 2017. Web. 16 Jun 2019.

Vancouver:

Bersano A. Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors. [Internet] [Thesis]. University of Illinois – Chicago; 2017. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/10027/21981.

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

Council of Science Editors:

Bersano A. Design of an Experimental Facility for Passive Heat Removal in Advanced Nuclear Reactors. [Thesis]. University of Illinois – Chicago; 2017. Available from: http://hdl.handle.net/10027/21981

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


EPFL

25. Girardin, Gaëtan. Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR).

Degree: 2009, EPFL

 During the past ten years, different independent factors, such as the rapidly increasing worldwide demand in energy, societal concerns about greenhouse gas emissions, and the… (more)

Subjects/Keywords: nuclear power plants; Generation IV; gas-cooled fast reactor (GFR); GCFR-PROTEUS; ERANOS-2.0; MCNPX; control assembly (CA) pattern; CA implementation scheme; FAST code system; TRACE; PARCS; transient analysis; 3D spatial kinetics; thermal-hydraulics; fuel cycle analysis; centrales nucléaires; Génération IV; réacteur à neutrons rapides refroidi au gaz (RNRG); GCFR-PROTEUS; MCNPX; design de l'assemblage de contrôle; schéma d'implantation; système de code FAST; TRACE; PARCS; analyse des transitoires; cinétique spatiale 3D; analyse du cycle du combustible

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

APA (6th Edition):

Girardin, G. (2009). Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR). (Thesis). EPFL. Retrieved from http://infoscience.epfl.ch/record/136746

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):

Girardin, Gaëtan. “Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR).” 2009. Thesis, EPFL. Accessed June 16, 2019. http://infoscience.epfl.ch/record/136746.

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

MLA Handbook (7th Edition):

Girardin, Gaëtan. “Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR).” 2009. Web. 16 Jun 2019.

Vancouver:

Girardin G. Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR). [Internet] [Thesis]. EPFL; 2009. [cited 2019 Jun 16]. Available from: http://infoscience.epfl.ch/record/136746.

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

Council of Science Editors:

Girardin G. Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR). [Thesis]. EPFL; 2009. Available from: http://infoscience.epfl.ch/record/136746

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


EPFL

26. Epiney, Aaron Simon. Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor.

Degree: 2010, EPFL

 Gas cooling in nuclear power plants (NPPs) has a long history, the corresponding reactor types developed in France, the UK and the US having been… (more)

Subjects/Keywords: Generation IV nuclear power plants; Gas-cooled Fast Reactor (GFR); decay heat removal (DHR); TRACE; CATHARE; EIR gas-loop experiments; FAST code system; transient analysis; heavy gas injection; Brayton cycle; Centrales nucléaires de Génération IV; Réacteur à Neutrons Rapides refroidi au Gaz (RNR-G); évacuation de la chaleur résiduelle; TRACE; CATHARE; expériences EIR de boucle à gaz; système de code FAST; analyse de transitoires; injection de gaz lourd; boucle de Brayton

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

APA (6th Edition):

Epiney, A. S. (2010). Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor. (Thesis). EPFL. Retrieved from http://infoscience.epfl.ch/record/149808

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):

Epiney, Aaron Simon. “Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor.” 2010. Thesis, EPFL. Accessed June 16, 2019. http://infoscience.epfl.ch/record/149808.

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

MLA Handbook (7th Edition):

Epiney, Aaron Simon. “Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor.” 2010. Web. 16 Jun 2019.

Vancouver:

Epiney AS. Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor. [Internet] [Thesis]. EPFL; 2010. [cited 2019 Jun 16]. Available from: http://infoscience.epfl.ch/record/149808.

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

Council of Science Editors:

Epiney AS. Improvement of the Decay Heat Removal Characteristics of the Generation IV Gas-cooled Fast Reactor. [Thesis]. EPFL; 2010. Available from: http://infoscience.epfl.ch/record/149808

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


EPFL

27. Chenu, Aurélia. Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors.

Degree: 2011, EPFL

Nuclear power is nowadays in the front rank as regards helping to meet the growing worldwide energy demand while avoiding an excessive increase in greenhouse… (more)

Subjects/Keywords: Sodium-cooled Fast Reactor (SFR); Generation-IV nuclear power plants; ESFR; safety demonstration; transient analysis; thermal-hydraulics; sodium two-phase flow; 3D neutron kinetics; FAST code system; TRACE; PARCS; sodium boiling experiments; Phenix tests; réacteur à neutrons rapides refroidi au sodium (RNR-Na); centrales nucléaires de Génération IV; ESFR; démonstration de sûreté; analyse de transitoires; thermo-hydraulique; écoulement sodium diphasique; cinétique neutronique 3D; système de codes FAST; TRACE; PARCS; expériences d'ébullition du sodium; tests Phénix

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

APA (6th Edition):

Chenu, A. (2011). Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors. (Thesis). EPFL. Retrieved from http://infoscience.epfl.ch/record/168639

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):

Chenu, Aurélia. “Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors.” 2011. Thesis, EPFL. Accessed June 16, 2019. http://infoscience.epfl.ch/record/168639.

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

MLA Handbook (7th Edition):

Chenu, Aurélia. “Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors.” 2011. Web. 16 Jun 2019.

Vancouver:

Chenu A. Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors. [Internet] [Thesis]. EPFL; 2011. [cited 2019 Jun 16]. Available from: http://infoscience.epfl.ch/record/168639.

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

Council of Science Editors:

Chenu A. Single- and Two-Phase Flow Modeling for Coupled Neutronics/Thermal-Hydraulics Transient Analysis of Advanced Sodium-Cooled Fast Reactors. [Thesis]. EPFL; 2011. Available from: http://infoscience.epfl.ch/record/168639

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


Brno University of Technology

28. Šimík, Michal. Moderní jaderné reaktory .

Degree: 2013, Brno University of Technology

 Táto bakalárska práca sa zaoberá vytvorením prehľadu typov jadrových reaktorov, ich históriou, súčasnosťou aj budúcnosťou. Veľká časť je zameraná na ciele požadované od moderných jadrových… (more)

Subjects/Keywords: Jadrový reaktor; jadrová elektráreň; štvrtá generácia; moderátor; chladivo; jadrové palivo; jadrová reakcia; jadrový odpad; Nuclear reactor; nuclear power plant; fourth generation; moderator; coolant; nuclear fuel; nuclear fission; nuclear waste

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

APA (6th Edition):

Šimík, M. (2013). Moderní jaderné reaktory . (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/27446

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):

Šimík, Michal. “Moderní jaderné reaktory .” 2013. Thesis, Brno University of Technology. Accessed June 16, 2019. http://hdl.handle.net/11012/27446.

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

MLA Handbook (7th Edition):

Šimík, Michal. “Moderní jaderné reaktory .” 2013. Web. 16 Jun 2019.

Vancouver:

Šimík M. Moderní jaderné reaktory . [Internet] [Thesis]. Brno University of Technology; 2013. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/11012/27446.

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

Council of Science Editors:

Šimík M. Moderní jaderné reaktory . [Thesis]. Brno University of Technology; 2013. Available from: http://hdl.handle.net/11012/27446

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

29. Wutzler, Whitney A. Analysis of Accidents in Sodium-Cooled Fast Reactors.

Degree: MS, Nuclear Engineering, 2011, The Ohio State University

  The research presented in this paper is part of a project to help develop a risk-informed approach to the design optimization and licensing of… (more)

Subjects/Keywords: Nuclear Engineering; Sodium Cooled; Fast Reactor; Accidents; Nuclear Reactor; Gen IV Reactor; SFR

…SFR designs have been created for the Generation IV Nuclear Energy Systems project. The… …generation costs for a Generation IV (Gen IV) sodium-cooled fast reactor (SFR)… …reactor designs that will meet the demand for clean and reliable power generation. Gen IV… …developing new reactor designs that meet the demand for clean and reliable power generation and… …precautionary design features put in place in a nuclear reactor, accidents can still occur. In… 

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

APA (6th Edition):

Wutzler, W. A. (2011). Analysis of Accidents in Sodium-Cooled Fast Reactors. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1306791253

Chicago Manual of Style (16th Edition):

Wutzler, Whitney A. “Analysis of Accidents in Sodium-Cooled Fast Reactors.” 2011. Masters Thesis, The Ohio State University. Accessed June 16, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1306791253.

MLA Handbook (7th Edition):

Wutzler, Whitney A. “Analysis of Accidents in Sodium-Cooled Fast Reactors.” 2011. Web. 16 Jun 2019.

Vancouver:

Wutzler WA. Analysis of Accidents in Sodium-Cooled Fast Reactors. [Internet] [Masters thesis]. The Ohio State University; 2011. [cited 2019 Jun 16]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1306791253.

Council of Science Editors:

Wutzler WA. Analysis of Accidents in Sodium-Cooled Fast Reactors. [Masters Thesis]. The Ohio State University; 2011. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1306791253


Georgia Tech

30. Matlack, Kathryn H. Nonlinear ultrasound for radiation damage detection.

Degree: PhD, Mechanical Engineering, 2014, Georgia Tech

 Radiation damage occurs in reactor pressure vessel (RPV) steel, causing microstructural changes such as point defect clusters, interstitial loops, vacancy-solute clusters, and precipitates, that cause… (more)

Subjects/Keywords: Nonlinear ultrasound; Second harmonic generation; Nondestructive evaluation; Radiation damage; Reactor pressure vessel steel; Structural health monitoring; Nondestructive testing; Nuclear pressure vessels

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

APA (6th Edition):

Matlack, K. H. (2014). Nonlinear ultrasound for radiation damage detection. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/51965

Chicago Manual of Style (16th Edition):

Matlack, Kathryn H. “Nonlinear ultrasound for radiation damage detection.” 2014. Doctoral Dissertation, Georgia Tech. Accessed June 16, 2019. http://hdl.handle.net/1853/51965.

MLA Handbook (7th Edition):

Matlack, Kathryn H. “Nonlinear ultrasound for radiation damage detection.” 2014. Web. 16 Jun 2019.

Vancouver:

Matlack KH. Nonlinear ultrasound for radiation damage detection. [Internet] [Doctoral dissertation]. Georgia Tech; 2014. [cited 2019 Jun 16]. Available from: http://hdl.handle.net/1853/51965.

Council of Science Editors:

Matlack KH. Nonlinear ultrasound for radiation damage detection. [Doctoral Dissertation]. Georgia Tech; 2014. Available from: http://hdl.handle.net/1853/51965

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