Numerical simulation of AP1000 LBLOCA with SCDAP/RELAP 4.0 code

被引:0
|
作者
Xie H. [1 ]
机构
[1] Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing
来源
Xie, Heng (xieheng@tsinghua.edu.cn) | 1600年 / Taylor and Francis Ltd.卷 / 54期
关键词
AP1000; LOCA; Numerical simulation; PWR type reactor; safety analysis; SCDAP/RELAP5;
D O I
10.1080/00223131.2017.1331766
中图分类号
学科分类号
摘要
The risk of large-break loss of coolant accident (LBLOCA) is that core will be exposed once the accident occurs, and may cause core damages. New phenomena may occur in LBLOCA due to passive safety injection adopted by AP1000. This paper used SCDAP/RELAP5 4.0 to build the numerical model of AP1000 and double-end guillotine of cold leg is simulated. Reactor coolant system and passive core cooling system were modeled by RELAP5 modular. HEAT STRUCTURE component of RELAP5 was used to simulate the fuel rod. The reflood option in RELAP5 was chosen to be activated or not to study the effect of axial heat conduction. Results show that the axial heat conduction plays an important role in the reflooding phase and can effectively shorten reflood process. An alternative core model is built by SCDAP modular. It is found that the SCDAP model predicts higher maximum peak cladding temperature and longer reflood process than RELAP5 model. Analysis shows that clad oxidation heat plays a key role in the reflood. From the simulation results, it can be concluded that the cladding will keep intact and fission product will not be released from fuel to coolant in LBLOCA. © 2017 Atomic Energy Society of Japan. All rights reserved.
引用
收藏
页码:969 / 976
页数:7
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