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

作     者：Liao, Haoyu Li, Chenxi He, Yanan Wu, Yingwei Zhang, Yapei Tian, Wenxi Su, G.H. Qiu, Suizheng 

作者机构：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'an710049 China 

出 版 物：《International Journal of Advanced Nuclear Reactor Design and Technology》 (Int. J. Adv. Nucl. React. Des. Technol.)

年 卷 期：2021年第3卷

页      面：54-65页

核心收录：

基　　金：This research has been supported by the National Key R&D Program of China (Grant No. 2019YFB1900700) 

主　　题：Loss of coolant accidents 

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