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雨忠
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50 积分
2024-01-29 加入
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Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel
1天前
待确认
Cask readied for spent nuclear fuel
2天前
已完结
FRAP-T6: A computer code for the transient analysis of oxide fuel rods
3天前
已完结
Development of Fuel ROd Behavior Analysis code (FROBA) and its application to AP1000
3天前
已完结
Core design of long‐cycle small modular lead‐cooled fast reactor
4天前
已完结
Spanish R&D in dry storage of spent fuel: Outcomes and outlook
4天前
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The core design of ALFRED, a demonstrator for the European lead-cooled reactors
10天前
已完结
Calculation model for core temperature field of miniature Pb-Bi cooled nuclear reactor
10天前
已完结
Evaluation of a Dual-Cooled Annular Fuel Heat Split and Temperature Distribution
10天前
已完结
CFD analysis of spent fuel dry cask storage system for High burnup nuclear fuel
13天前
已完结
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