SODIUM COOLED FAST BREAD REACTOR HCDA CODES DEVELOPMENT

被引：0
|
作者：
Shi Tai [1 ]
Zhang Dong-hui [1 ]
Hu Wen-jun [1 ]
机构：
[1] China Inst Atom Energy, Beijing, Peoples R China
来源：
PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 5 | 2017年
关键词：
RECRITICALITY; ELIMINATION;
D O I：
暂无
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
Liquid metal fast reactor is one of the Gen IV nuclear power, it is necessary to analyze hypothetical core disruptive accident (HCDA) of FBR to ensure that the system can prevent the radioactive material from leaking out. The modified Bethe-Tait model is the primary method to analyze hypothetical core disruptive accident in the world. In order to better analyze the nuclear reactor hypothetical core disruptive accident in China, an improved B-T model is used. At present, on the basis of the improved B-T model, power distribution of the CEFR add to the progress. The results of comparison between the program and SUREX program in France show that the program model can simulate the nuclear reactor hypothetical core disruptive accident in China.
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页数：7
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