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Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2020.07.008] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Castro L, François JL, García C. Coupled Monte Carlo-burnup and CFD analysis of coated UN and UC fuels in an HPLWR fuel assembly. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2020.103342] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Zhou S, Cao L, Wu H, Bai B, Lei C, Zhang Y. SPARK-LS: A novel design of a compact liquid chloride salt cooled fast reactor based on tube-in-duct fuel concept. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.01.020] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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Allen DJ, Blair SR, Millett MG, Nelson ME. Evaluation of Non-Oxide Fuel for Fission-Based Nuclear Reactors on Spacecraft. NUCL TECHNOL 2018. [DOI: 10.1080/00295450.2018.1524228] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
Affiliation(s)
- Dakota J. Allen
- United States Naval Academy, Mechanical Engineering Department, 590 Holloway Road, Annapolis, Maryland 21402
| | - Stuart R. Blair
- United States Naval Academy, Mechanical Engineering Department, 590 Holloway Road, Annapolis, Maryland 21402
| | - Marshall G. Millett
- United States Naval Academy, Mechanical Engineering Department, 590 Holloway Road, Annapolis, Maryland 21402
| | - Martin E. Nelson
- United States Naval Academy, Mechanical Engineering Department, 590 Holloway Road, Annapolis, Maryland 21402
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Jolkkonen M, Malkki P, Johnson K, Wallenius J. Uranium nitride fuels in superheated steam. J NUCL SCI TECHNOL 2017. [DOI: 10.1080/00223131.2017.1291372] [Citation(s) in RCA: 22] [Impact Index Per Article: 3.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- Mikael Jolkkonen
- Department of Reactor Physics, Royal Institute of Technology, Alba Nova University Center, Stockholm, Sweden
| | - Pertti Malkki
- Department of Reactor Physics, Royal Institute of Technology, Alba Nova University Center, Stockholm, Sweden
| | - Kyle Johnson
- Department of Reactor Physics, Royal Institute of Technology, Alba Nova University Center, Stockholm, Sweden
| | - Janne Wallenius
- Department of Reactor Physics, Royal Institute of Technology, Alba Nova University Center, Stockholm, Sweden
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Ahmed H, Chaudri KS, Mirza SM. Comparative analyses of coated and composite UN fuel – Monte Carlo based full core LWR study. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2016.08.014] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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Kheradmand Saadi M, Bashiri B. Neutronic and thermal-hydraulic analysis of alternative ceramic fuels in the next-generation of light water reactors. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2015.11.002] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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Brown NR, Aronson A, Todosow M, Brito R, McClellan KJ. Neutronic performance of uranium nitride composite fuels in a PWR. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.04.040] [Citation(s) in RCA: 45] [Impact Index Per Article: 4.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Savchenko A, Vatulin A, Kulakov G, Lipkina K, Sorokin V, Morozov A, Ershov S, Uferov O, Mainikov E, Kozlov A. Peculiarities of fuel cycle with advanced composite fuel for thermal reactors. PROGRESS IN NUCLEAR ENERGY 2014. [DOI: 10.1016/j.pnucene.2013.10.007] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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Chaudri KS, Tian W, Su Y, Zhao H, Zhu D, Su G, Qiu S. Coupled analysis for new fuel design using UN and UC for SCWR. PROGRESS IN NUCLEAR ENERGY 2013. [DOI: 10.1016/j.pnucene.2012.11.001] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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