The investigation of Passive Accident Mitigation Scheme for advanced PWR NPP

Shi Er-bing; Fang Cheng-yue; Wang Chang; Xia Geng-lei; Zhao Cui-na

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The investigation of Passive Accident Mitigation Scheme for advanced PWR NPP

机译：先进压水堆核电厂被动事故缓解方案的研究

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To enhance inherent safety features of nuclear power plant, the advanced pressurized water reactors implement a series of passive safety systems. This paper puts forward and designs a new Passive Accident Mitigation Scheme (PAMS) to remove residual heat, which consists of two parts: the first part is Passive Auxiliary Feedwater System (PAFS), and the other part is Passive Heat Removal System (PHRS).

机译：为了增强核电厂的固有安全特性，先进的压水堆采用了一系列被动安全系统。本文提出并设计了一种新的消除残留热量的被动事故缓解方案（PAMS），该方案包括两部分：第一部分是被动辅助给水系统（PAFS），第二部分是被动排热系统（PHRS）。

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来源
《Annals of nuclear energy》 |2015年第11期|590-596|共7页
作者
Shi Er-bing; Fang Cheng-yue; Wang Chang; Xia Geng-lei; Zhao Cui-na;
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作者单位

China Ship Dev & Design Ctr, Wuhan 430000, Peoples R China;

China Ship Dev & Design Ctr, Wuhan 430000, Peoples R China;

China Ship Dev & Design Ctr, Wuhan 430000, Peoples R China;

Harbin Engn Univ, Harbin 150001, Peoples R China;

China Ship Dev & Design Ctr, Wuhan 430000, Peoples R China;

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原文格式 PDF
正文语种 eng
中图分类
关键词
PAMS; Station Blackout Accident; RELAP5;

机译：PAMS;车站停电事故;RELAP5;

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1. Performance verification of Passive Accident Mitigation Scheme (PAMS) under feedwater line break (FLB) accident [J] . Shi Er-bing, Wang Chang, Hao Rui, Annals of nuclear energy . 2017,第nova期

机译：给水线路中断（FLB）事故下的被动事故缓解方案（PAMS）的性能验证
2. STUDY ON HEAT REMOVAL CAPACITY OF PCCS OF ADVANCED PASSIVE PWR DURING SEVERE ACCIDENTS [J] . LILI TONG, JIE ZOU, JUN TAO, Nuclear Technology . 2015,第1期

机译：严重事故下高级被动压水堆PCCS的除热能力研究
3. Simulation of fission products behavior in severe accidents for advanced passive PWR [J] . L.L. Tong, G.F. Huang, X.W. Cao Annals of nuclear energy . 2015,第feba期

机译：高级被动式压水堆在严重事故中裂变产物行为的仿真
4. Safety assessment of severe accident mitigating system “Passive Residual Heat Removal System of secondary side” in K-2/K-3 NPP [C] . Muhammad Abu Bakar, Muhammad Sohail Sarwar International Conference on Emerging Technologies . 2016

机译：K-2 / K-3核电厂严重事故缓解系统“二次侧被动余热排除系统”的安全性评估
5. Joining of Silicon Carbide for Accident Tolerant PWR Fuel Cladding [D] . Paul, James. 2017

机译：加入耐事故压水堆覆层的碳化硅
6. Comparative analysis of the countermeasures taken to mitigate exposure of the public to radioiodine following the Chernobyl and Fukushima accidents: lessons from both accidents [O] . Vladimir Uyba, Alexander Samoylov, Sergey Shinkarev 2018

机译：切尔诺贝利事故和福岛事故后为减轻公众暴露于放射性碘而采取的对策的比较分析：两次事故的教训
7. Design Scheme Investigation of PWR Passive Residual Heat Removal System [O] . 协宇魏 2017

机译：PWR无源残余散热系统的设计方案研究

The investigation of Passive Accident Mitigation Scheme for advanced PWR NPP

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