The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA

作     者：Wang, Jun Fan, Yuqiao Zhang, Yapei Ni, Xinghe Tian, Wenxi Corradini, Michael L. Su, Guanghui Qiu, Suizheng 

作者机构：State Key Laboratory of Multiphase Flow in Power Engineering Department of Nuclear Science and Technology Xi’an Jiaotong University Xi’an 710049 China College of Engineering University of Wisconsin-Madison Madison WI 53706 

出 版 物：《Journal of Nuclear Engineering and Radiation Science》 

年 卷 期：2016年第2卷第2期

页      面：021002页

学科分类：08[工学] 0827[工学-核科学与技术] 

主　　题：Melting MIDAC CPR1000 Vessels MAAP severe accident Flow (Dynamics) Accidents LOCA Temperature Hydrogen 

摘      要：The occurrence of Fukushima has increased the focus on the development of severe accident codes and their applications. As a part of Chinese “National Major Projects, a module in-vessel degraded analysis code (MIDAC) is currently being developed at Xi’an Jiaotong University. The developing situation of a candling module and relevant calculation for CPR1000 for large break loss of coolant analysis (LOCA) are presented in this paper. The candling module focuses on the melting, moving, and relocation of the melting core materials and necessary thermal hydraulic information. MIDAC’s LOCA accident calculation results of Chinese pressure reactor 1000 (CPR1000) cover the melting mass distribution, peak temperature, and hydrogen generation. The results have been compared with MAAP. Through comparison, the candling module of MIDAC proved to be able to predict the moving trend of the molten material mass relocation in the reactor pressure vessel.