Innovative model of annular fuel design for lead-cooled fast reactors
被引:7
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作者:
Rowinski, Marcin Karol
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Nanyang Technol Univ, Interdisciplinary Grad Sch, Energy Res Inst NTU, Singapore 639798, Singapore
Nanyang Technol Univ, Sch Elect & Elect Engn, Ctr E City, EXQUISITUS, Singapore 639798, SingaporeNanyang Technol Univ, Interdisciplinary Grad Sch, Energy Res Inst NTU, Singapore 639798, Singapore
Rowinski, Marcin Karol
[1
,2
]
White, Timothy John
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Nanyang Technol Univ, Interdisciplinary Grad Sch, Energy Res Inst NTU, Singapore 639798, SingaporeNanyang Technol Univ, Interdisciplinary Grad Sch, Energy Res Inst NTU, Singapore 639798, Singapore
White, Timothy John
[1
]
Zhao, Jiyun
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City Univ Hong Kong, Dept Mech & Biomed Engn, Kowloon, Hong Kong, Peoples R ChinaNanyang Technol Univ, Interdisciplinary Grad Sch, Energy Res Inst NTU, Singapore 639798, Singapore
Zhao, Jiyun
[3
]
机构:
[1] Nanyang Technol Univ, Interdisciplinary Grad Sch, Energy Res Inst NTU, Singapore 639798, Singapore
[2] Nanyang Technol Univ, Sch Elect & Elect Engn, Ctr E City, EXQUISITUS, Singapore 639798, Singapore
[3] City Univ Hong Kong, Dept Mech & Biomed Engn, Kowloon, Hong Kong, Peoples R China
The results of an investigation of the analytical solutions of the default solid fuel and innovative annular fuel approach are summarized in this paper. Innovative annular fuel concept is described in details and shows that it is a promising technology in terms of safety aspects. Liquid metal cooled reactors are considered to burn used nuclear fuel from conventional nuclear power plants or processed weapon grade plutonium and therefore, higher safety standards must be assured. During the design process seven fuel assemblies with annular fuel elements were created. The investigation was conducted in case of both commonly used fuel lattices i.e. square and hexagonal, moreover effect of spacer grids was taken into considerations. Results show that the annular fuel is superior in case of maximum fuel temperature, which is up to 757 degrees C lower than in default base design with use of spacer grids. The most promising designs are hexagonal lattice with 91 fuel elements and square lattice 18 x 18, where the maximum temperatures are 822 degrees C and 732 degrees C, while pressure drop of 185 kPa and 128 kPa, respectively. The square lattice proved better performance according to our evaluation, it is possible to obtain very similar or smaller pressure drop than default solid fuel design. Hence, use of the same or even smaller coolant pumps is possible in case of annular fuel elements. Moreover, the innovative fuel also allows to overpower reactor up to 110% of nominal power, while securing all safety limits. Therefore, it is promising concept and further investigation would be interesting. (C) 2015 Elsevier Ltd. All rights reserved.
机构:
Tokyo Inst Technol, Inst Innovat Res, Lab Zero Carbon Energy, 2-12-1-N1-19 Ookayama,Meguroku, Tokyo 1528550, JapanTokyo Inst Technol, Inst Innovat Res, Lab Zero Carbon Energy, 2-12-1-N1-19 Ookayama,Meguroku, Tokyo 1528550, Japan
Stafie, Alexandru Catalin
Nishiyama, Jun
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Tokyo City Univ, Dept Nucl Safety Engn, 1281 Tamazutsumi,Setagaya Ku, Tokyo 1588557, JapanTokyo Inst Technol, Inst Innovat Res, Lab Zero Carbon Energy, 2-12-1-N1-19 Ookayama,Meguroku, Tokyo 1528550, Japan
机构:
North Carolina State Univ, Dept Nucl Engn, Burlington Engn Lab, 2500 Stinson Dr, Raleigh, NC 27695 USANorth Carolina State Univ, Dept Nucl Engn, Burlington Engn Lab, 2500 Stinson Dr, Raleigh, NC 27695 USA
Hou, Jason
Grasso, Giacomo
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ENEA, FSN, SICNUC, PSSN, V Martiri di Monte Sole 4, I-40129 Bologna, ItalyNorth Carolina State Univ, Dept Nucl Engn, Burlington Engn Lab, 2500 Stinson Dr, Raleigh, NC 27695 USA
Grasso, Giacomo
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Ivanov, Kostadin
Franceschini, Fausto
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Westinghouse Mangiarotti SPA, V Timavo 59, I-34074 Monfalcone, ItalyNorth Carolina State Univ, Dept Nucl Engn, Burlington Engn Lab, 2500 Stinson Dr, Raleigh, NC 27695 USA
机构:
Univ Nacl Autonoma Mexico, Fac Ingn, Mexico City 04510, DF, MexicoUniv Nacl Autonoma Mexico, Fac Ingn, Mexico City 04510, DF, Mexico
Centeno-Perez, J.
Perez-Valseca, A. D.
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Univ Autonoma Metropolitana Iztapalapa, Area Ingn Recursos Energet, Mexico City 09340, DF, MexicoUniv Nacl Autonoma Mexico, Fac Ingn, Mexico City 04510, DF, Mexico
Perez-Valseca, A. D.
Gomez-Torres, A.
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机构:
Inst Nacl Invest Nucl, Ocoyoacac 52750, Estado De Mexic, MexicoUniv Nacl Autonoma Mexico, Fac Ingn, Mexico City 04510, DF, Mexico
Gomez-Torres, A.
Lopez-Solis, R. C.
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Inst Nacl Invest Nucl, Ocoyoacac 52750, Estado De Mexic, MexicoUniv Nacl Autonoma Mexico, Fac Ingn, Mexico City 04510, DF, Mexico
Lopez-Solis, R. C.
Vazquez-Rodriguez, A.
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Univ Autonoma Metropolitana Iztapalapa, Area Ingn Recursos Energet, Mexico City 09340, DF, MexicoUniv Nacl Autonoma Mexico, Fac Ingn, Mexico City 04510, DF, Mexico
Vazquez-Rodriguez, A.
Espinosa-Paredes, G.
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Univ Autonoma Metropolitana Iztapalapa, Area Ingn Recursos Energet, Mexico City 09340, DF, MexicoUniv Nacl Autonoma Mexico, Fac Ingn, Mexico City 04510, DF, Mexico