Practical Design of a Breed-and-Burn Lead-Cooled Fast Reactor with Rotational Fuel Shuffling Strategy
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Stafie, Alexandru Catalin
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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
[1
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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
Nishiyama, Jun
[2
]
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Obara, Toru
[1
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[1] Tokyo Inst Technol, Inst Innovat Res, Lab Zero Carbon Energy, 2-12-1-N1-19 Ookayama,Meguroku, Tokyo 1528550, Japan
[2] Tokyo City Univ, Dept Nucl Safety Engn, 1281 Tamazutsumi,Setagaya Ku, Tokyo 1588557, Japan
The purpose of this study is to demonstrate a practical core design for a lead-cooled, nitride fueled, rotational fuel shuffling breed-and-burn (RFBB) fast reactor. The core design is based on the Westinghouse Lead Fast Reactor (WH-LFR) and uses natural uranium nitride fuel with a sodium bond encased in oxide dispersion-strengthened steel cladding. Simulations confirmed the potential of the reactor to maintain criticality at the equilibrium state, with a reactivity swing of less than 200 pcm at every cycle interval and an average discharge burnup of 235 MWd/kg heavy metals (HM) for a 1050 effective full-power day refueling interval. Power profiles were maintained stable at the equilibrium state, while the cladding of the discharged fuel incurred over 650 displacements per atom over its entire residency in the core. From a nonproliferation perspective, the plutonium vector for the discharge fuel aligns with reactor-grade fuel standards, with over a 70% concentration of Pu-239 and over 22% Pu-240, reducing the risk of weaponization. The adopted control rod system has been shown to offer sufficient negative reactivity of over 19 $ to bring the reactor into a subcritical state. Challenges such as the susceptibility of neutron balance to material thickness and neutron leakage have been addressed, emphasizing the necessity for meticulous design improvements. A steady-state thermohydraulic analysis confirmed the heat removal capacity from the hottest channel, ensuring operational safety. This study confirmed the feasibility of the RFBB strategy for a lead-cooled nitride-fueled fast reactor and sets a precedent for future research in enhancing fuel utilization and safety in nuclear reactors.
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North China Elect Power Univ, Sch Energy Power & Mech Engn, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Nucl Thermal Safety & Standardizat Res Inst, Beijing 102206, Peoples R China
Qin, Li
Imam, Syed Suleman
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North China Elect Power Univ, Nucl Thermal Safety & Standardizat Res Inst, Beijing 102206, Peoples R ChinaNorth China Elect Power Univ, Nucl Thermal Safety & Standardizat Res Inst, Beijing 102206, Peoples R China
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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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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