Lv12
30 积分 2025-12-15 加入
Preliminary study on the postulated siting accident source term of integrated small reactor
1天前
求助中
Analysis of full-scale thermal-hydraulic characteristics of sodium-cooled fast reactor core under steady-state and accident scenarios
1天前
已完结
Preliminary analysis of maximum hypothetical accident for a solid core space nuclear reactor power system
1天前
求助中
基于MELCOR软件的船用反应堆事故进程分析研究
1天前
已完结
小型堆断电严重事故缓解措施分析
1天前
已完结
基于MELCOR1.8.5的反应堆严重事故分析
1天前
已完结
Burst Criterion of Zircaloy Fuel Claddings in a Loss-of-Coolant Accident
2个月前
已完结
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