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You searched for subject:(Molten salt reactors). Showing records 1 – 10 of 10 total matches.

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University of Illinois – Urbana-Champaign

1. Rykhlevskii, Andrei. Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor.

Degree: MS, Nuclear, Plasma, Radiolgc Engr, 2018, University of Illinois – Urbana-Champaign

 Current interest in advanced nuclear energy and MSR concepts has enhanced demand in building the tools to analyze these systems. This thesis introduces a Python… (more)

Subjects/Keywords: molten salt reactors; MSR; MSBR; thorium; fuel cycle; online reprocessing

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APA (6th Edition):

Rykhlevskii, A. (2018). Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/101052

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):

Rykhlevskii, Andrei. “Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor.” 2018. Thesis, University of Illinois – Urbana-Champaign. Accessed August 18, 2019. http://hdl.handle.net/2142/101052.

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

MLA Handbook (7th Edition):

Rykhlevskii, Andrei. “Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor.” 2018. Web. 18 Aug 2019.

Vancouver:

Rykhlevskii A. Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2018. [cited 2019 Aug 18]. Available from: http://hdl.handle.net/2142/101052.

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

Council of Science Editors:

Rykhlevskii A. Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor. [Thesis]. University of Illinois – Urbana-Champaign; 2018. Available from: http://hdl.handle.net/2142/101052

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


The Ohio State University

2. Chaleff, Ethan S. The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors.

Degree: PhD, Nuclear Engineering, 2016, The Ohio State University

Molten salts, such as the fluoride salt eutectic LiF-NaF-KF (FLiNaK) or the transition metal fluoride salt KF-ZrF4, have been proposed as coolants for numerous advanced… (more)

Subjects/Keywords: Nuclear Engineering; molten salt; radiative heat transfer; nuclear reactor; advanced reactors; salt-cooled reactor; density functional theory; DFT

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APA (6th Edition):

Chaleff, E. S. (2016). The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1480539289737113

Chicago Manual of Style (16th Edition):

Chaleff, Ethan S. “The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors.” 2016. Doctoral Dissertation, The Ohio State University. Accessed August 18, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1480539289737113.

MLA Handbook (7th Edition):

Chaleff, Ethan S. “The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors.” 2016. Web. 18 Aug 2019.

Vancouver:

Chaleff ES. The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors. [Internet] [Doctoral dissertation]. The Ohio State University; 2016. [cited 2019 Aug 18]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1480539289737113.

Council of Science Editors:

Chaleff ES. The Radiative Heat Transfer Properties of Molten Salts and Their Relevance to the Design of Advanced Reactors. [Doctoral Dissertation]. The Ohio State University; 2016. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1480539289737113


University of California – Berkeley

3. Blandford, Edward David. Physical Similitude in Hierarchical Engineered Systems.

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

 Engineers interested in predicting the behavior of complex engineered systems have a strong need to prioritize phenomena by importance due to limitations in simulation and… (more)

Subjects/Keywords: Nuclear Engineering; Fractional scaling analysis; Hierarchical engineered systems; Molten salt reactors; Physical similitude; Reduced-scale experiments; Simulant fluids

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APA (6th Edition):

Blandford, E. D. (2010). Physical Similitude in Hierarchical Engineered Systems. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/5gf44031

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):

Blandford, Edward David. “Physical Similitude in Hierarchical Engineered Systems.” 2010. Thesis, University of California – Berkeley. Accessed August 18, 2019. http://www.escholarship.org/uc/item/5gf44031.

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

MLA Handbook (7th Edition):

Blandford, Edward David. “Physical Similitude in Hierarchical Engineered Systems.” 2010. Web. 18 Aug 2019.

Vancouver:

Blandford ED. Physical Similitude in Hierarchical Engineered Systems. [Internet] [Thesis]. University of California – Berkeley; 2010. [cited 2019 Aug 18]. Available from: http://www.escholarship.org/uc/item/5gf44031.

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

Council of Science Editors:

Blandford ED. Physical Similitude in Hierarchical Engineered Systems. [Thesis]. University of California – Berkeley; 2010. Available from: http://www.escholarship.org/uc/item/5gf44031

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


Brno University of Technology

4. 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 August 18, 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. 18 Aug 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 Aug 18]. 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 Missouri – Columbia

5. Schwarz, Eric A., 1979-. Technology for restarting molten salt nuclear fuel chemistry at MU.

Degree: 2011, University of Missouri – Columbia

 Nuclear fuel reprocessing is a responsible choice for the continued expansion of a secure, safe and clean source of energy. While the classical method for… (more)

Subjects/Keywords: Alpha-bearing wastes; Actinide elements; Molten salt reactors; Nuclear fuels; Radioactive waste disposal; Rare earth metals  – Recycling

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APA (6th Edition):

Schwarz, Eric A., 1. (2011). Technology for restarting molten salt nuclear fuel chemistry at MU. (Thesis). University of Missouri – Columbia. Retrieved from http://hdl.handle.net/10355/11506

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):

Schwarz, Eric A., 1979-. “Technology for restarting molten salt nuclear fuel chemistry at MU.” 2011. Thesis, University of Missouri – Columbia. Accessed August 18, 2019. http://hdl.handle.net/10355/11506.

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

MLA Handbook (7th Edition):

Schwarz, Eric A., 1979-. “Technology for restarting molten salt nuclear fuel chemistry at MU.” 2011. Web. 18 Aug 2019.

Vancouver:

Schwarz, Eric A. 1. Technology for restarting molten salt nuclear fuel chemistry at MU. [Internet] [Thesis]. University of Missouri – Columbia; 2011. [cited 2019 Aug 18]. Available from: http://hdl.handle.net/10355/11506.

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

Council of Science Editors:

Schwarz, Eric A. 1. Technology for restarting molten salt nuclear fuel chemistry at MU. [Thesis]. University of Missouri – Columbia; 2011. Available from: http://hdl.handle.net/10355/11506

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


Colorado School of Mines

6. Alameri, Saeed A. Coupled nuclear reactor thermal energy storage system for enhanced load following operation, A.

Degree: PhD, Metallurgical and Materials Engineering, 2007, Colorado School of Mines

 Nuclear power plants usually provide base-load electric power and operate most economically at a constant power level. In an energy grid with a high fraction… (more)

Subjects/Keywords: Molten salt reactor; Thermal energy storage; Safety assessment; Nuclear power plants; Heat storage; Nuclear reactors; Energy storage; Molten salt reactors

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APA (6th Edition):

Alameri, S. A. (2007). Coupled nuclear reactor thermal energy storage system for enhanced load following operation, A. (Doctoral Dissertation). Colorado School of Mines. Retrieved from http://hdl.handle.net/11124/17109

Chicago Manual of Style (16th Edition):

Alameri, Saeed A. “Coupled nuclear reactor thermal energy storage system for enhanced load following operation, A.” 2007. Doctoral Dissertation, Colorado School of Mines. Accessed August 18, 2019. http://hdl.handle.net/11124/17109.

MLA Handbook (7th Edition):

Alameri, Saeed A. “Coupled nuclear reactor thermal energy storage system for enhanced load following operation, A.” 2007. Web. 18 Aug 2019.

Vancouver:

Alameri SA. Coupled nuclear reactor thermal energy storage system for enhanced load following operation, A. [Internet] [Doctoral dissertation]. Colorado School of Mines; 2007. [cited 2019 Aug 18]. Available from: http://hdl.handle.net/11124/17109.

Council of Science Editors:

Alameri SA. Coupled nuclear reactor thermal energy storage system for enhanced load following operation, A. [Doctoral Dissertation]. Colorado School of Mines; 2007. Available from: http://hdl.handle.net/11124/17109

7. Flanders, Justin M. Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept.

Degree: MS, Nuclear Engineering, 2012, The Ohio State University

 Surface power and nuclear electric propulsion in space necessitate the development of high energy density, long term continuous power sources. Research at The Ohio State… (more)

Subjects/Keywords: Nuclear Engineering; molten salt; molten salt reactors; NASA; space nuclear; Brayton; heat exchanger; offset strip fin

…Opportunity has identified molten salt reactors (MSRs) as a potentially appealing… …4 1.3. Background on Molten Salt Reactors 1.3.1. Fuel Structure and Heat Removal A… …of MSRs When discussing molten salt reactors, it is important to discuss the design… …On terrestrial molten salt reactors, valving was accomplished by melting and freezing… …continues to develop the Space Molten Salt Reactor concept (SMSR) by examining… 

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APA (6th Edition):

Flanders, J. M. (2012). Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1345508695

Chicago Manual of Style (16th Edition):

Flanders, Justin M. “Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept.” 2012. Masters Thesis, The Ohio State University. Accessed August 18, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1345508695.

MLA Handbook (7th Edition):

Flanders, Justin M. “Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept.” 2012. Web. 18 Aug 2019.

Vancouver:

Flanders JM. Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept. [Internet] [Masters thesis]. The Ohio State University; 2012. [cited 2019 Aug 18]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1345508695.

Council of Science Editors:

Flanders JM. Thermal Transport and Heat Exchanger Design for the Space Molten Salt Reactor Concept. [Masters Thesis]. The Ohio State University; 2012. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1345508695


University of Cambridge

8. 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 August 18, 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. 18 Aug 2019.

Vancouver:

Kasam A. Conceptual design of a breed & burn molten salt reactor. [Internet] [Doctoral dissertation]. University of Cambridge; 2019. [cited 2019 Aug 18]. 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

9. Gros, Emilien B. Liquid-Salt-Cooled Reactor start-up with natural circulation under Loss-of-Offsite-Power (LOOP) conditions.

Degree: MS, Nuclear and Radiological Engineering, 2012, Georgia Tech

 The Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) was modeled using the neutronics analysis code SCALE6.0 and the thermal-hydraulics and kinetics modeling code RELAP5-3D with objective to… (more)

Subjects/Keywords: Liquid-salt; Reactor; Start-up; Loss of offsite power; Molten salt reactors; Nuclear power plants Power supply; Electric power failures

…regions during the start-up 74 xi LIST OF SYMBOLS AND ABBREVIATIONS LS-VHTR Liquid-Salt… …Analysis Program INL Idaho National Laboratory LWR Light Water Reactors RVACS Reactor… …Heat Removal System xii SUMMARY The Liquid-Salt-Cooled Very High-Temperature Reactor… …Liquid-Salt-Cooled Very High-Temperature Reactor (LS-VHTR) is one of the six concepts… …of Generation IV reactors [1]. It has conceptually many promising features and… 

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APA (6th Edition):

Gros, E. B. (2012). Liquid-Salt-Cooled Reactor start-up with natural circulation under Loss-of-Offsite-Power (LOOP) conditions. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/43745

Chicago Manual of Style (16th Edition):

Gros, Emilien B. “Liquid-Salt-Cooled Reactor start-up with natural circulation under Loss-of-Offsite-Power (LOOP) conditions.” 2012. Masters Thesis, Georgia Tech. Accessed August 18, 2019. http://hdl.handle.net/1853/43745.

MLA Handbook (7th Edition):

Gros, Emilien B. “Liquid-Salt-Cooled Reactor start-up with natural circulation under Loss-of-Offsite-Power (LOOP) conditions.” 2012. Web. 18 Aug 2019.

Vancouver:

Gros EB. Liquid-Salt-Cooled Reactor start-up with natural circulation under Loss-of-Offsite-Power (LOOP) conditions. [Internet] [Masters thesis]. Georgia Tech; 2012. [cited 2019 Aug 18]. Available from: http://hdl.handle.net/1853/43745.

Council of Science Editors:

Gros EB. Liquid-Salt-Cooled Reactor start-up with natural circulation under Loss-of-Offsite-Power (LOOP) conditions. [Masters Thesis]. Georgia Tech; 2012. Available from: http://hdl.handle.net/1853/43745


University of Cambridge

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

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

APA (6th Edition):

Kasam, A. (n.d.). Conceptual design of a breed & burn molten salt reactor . (Thesis). University of Cambridge. Retrieved from https://www.repository.cam.ac.uk/handle/1810/289755

Note: this citation may be lacking information needed for this citation format:
No year of publication.
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Kasam, Alisha. “Conceptual design of a breed & burn molten salt reactor .” Thesis, University of Cambridge. Accessed August 18, 2019. https://www.repository.cam.ac.uk/handle/1810/289755.

Note: this citation may be lacking information needed for this citation format:
No year of publication.
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Kasam, Alisha. “Conceptual design of a breed & burn molten salt reactor .” Web. 18 Aug 2019.

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

Vancouver:

Kasam A. Conceptual design of a breed & burn molten salt reactor . [Internet] [Thesis]. University of Cambridge; [cited 2019 Aug 18]. Available from: https://www.repository.cam.ac.uk/handle/1810/289755.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
No year of publication.

Council of Science Editors:

Kasam A. Conceptual design of a breed & burn molten salt reactor . [Thesis]. University of Cambridge; Available from: https://www.repository.cam.ac.uk/handle/1810/289755

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation
No year of publication.

.