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机译:高温气体冷却反应器中核应急响应的快速事故源术语估计(Raste)
Tsinghua Univ Inst Nucl & New Energy Technol Beijing 100084 Peoples R China|Tsinghua Univ Collaborat Innovat Ctr Adv Nucl Energy Technol Beijing 100084 Peoples R China|Minist Educ Key Lab Adv Reactor Engn & Safety Beijing 100084 Peoples R China;
Tsinghua Univ Inst Nucl & New Energy Technol Beijing 100084 Peoples R China|Tsinghua Univ Collaborat Innovat Ctr Adv Nucl Energy Technol Beijing 100084 Peoples R China|Minist Educ Key Lab Adv Reactor Engn & Safety Beijing 100084 Peoples R China;
Tsinghua Univ Inst Nucl & New Energy Technol Beijing 100084 Peoples R China|Tsinghua Univ Collaborat Innovat Ctr Adv Nucl Energy Technol Beijing 100084 Peoples R China|Minist Educ Key Lab Adv Reactor Engn & Safety Beijing 100084 Peoples R China;
Tsinghua Univ Inst Nucl & New Energy Technol Beijing 100084 Peoples R China|Tsinghua Univ Collaborat Innovat Ctr Adv Nucl Energy Technol Beijing 100084 Peoples R China|Minist Educ Key Lab Adv Reactor Engn & Safety Beijing 100084 Peoples R China;
Tsinghua Univ Inst Nucl & New Energy Technol Beijing 100084 Peoples R China|Tsinghua Univ Collaborat Innovat Ctr Adv Nucl Energy Technol Beijing 100084 Peoples R China|Minist Educ Key Lab Adv Reactor Engn & Safety Beijing 100084 Peoples R China;
Source term estimation; Nuclear emergency; Decision-making system; High temperature gas-cooled reactor; HTR-PM;
机译:基于贝叶斯网络的加压水反应器核事故应急决策快速源期估算研究
机译:在事故条件下高温气体冷却反应器源期评价的不确定性分析 - 鉴定强制循环事故中的影响因素
机译:核电站事故的前向后耦合源项估计:冷却液损失事故情景的案例研究
机译:事故条件下高温气冷堆源头评估的不确定性分析-强迫循环事故中影响因素的识别
机译:高温气冷反应堆的反应堆腔冷却系统中的结垢方法和热工水力分析,以及钠快速反应堆中的热喷射混合。
机译:纽约市核反应堆事故应急计划的某些方面。
机译:图2来自:Bulakh Oi,Kostyyh OK,Nesterov VN,Cherdizov Ek(2019)延长高温气体冷却反应堆燃料块中石墨的寿命,作为确保核燃料燃烧的设计价值的资源。核能和技术5(4):289-295。 https://doi.org/10.3897/nucet.5.48391
机译:气冷堆数据库在LWR事故辐照源项估算中的应用