Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code

被引：0
|
作者：
Liao H. [1 ]
Li C. [1 ]
He Y. [1 ]
Wu Y. [1 ]
Zhang Y. [1 ]
Tian W. [1 ]
Su G.H. [1 ]
Qiu S. [1 ]
机构：
[1] School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an
来源：
International Journal of Advanced Nuclear Reactor Design and Technology | 2021年 / 3卷
关键词：
Cladding failure; Cladding oxidation; Failure threshold; FROBA-ROD; High-temperature creep; Loss of coolant accident;
D O I：
10.1016/j.jandt.2021.06.003
中图分类号：
学科分类号：
摘要：
Loss of Coolant Accident (LOCA) is one of the major design-basis accidents in LWRs. Fuel rod may fail due to the rupture of the cladding. By developing a LOCA simulation module, the steady-state fuel rod performance analysis code, FROBA-ROD, is now capable to predict fuel rod behaviors under a LOCA transient. The relevant models and the code was verified and validated by comparing with authoritative commercial codes and with the experimental measurements. Comprehensive calculations and analyses of fuel rod behaviors under different LOCA transients were performed by the new version of FROBA-ROD. Compared the failure conditions to the non-failure conditions through the simulation results, a cladding failure threshold equation was found for a better estimate of the integrity of high burnup fuel rods under LOCA transients. © 2021 Xi'an Jiaotong University
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收藏
页码：54 / 65
页数：11
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