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.
The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA
Manuscript received January 27, 2015; final manuscript received October 17, 2015; published online February 29, 2016. Assoc. Editor: Xu Cheng.
- Views Icon Views
- Share Icon Share
- Cite Icon Cite
- Search Site
Wang, J., Fan, Y., Zhang, Y., Ni, X., Tian, W., Corradini, M. L., Su, G., and Qiu, S. (February 29, 2016). "The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA." ASME. ASME J of Nuclear Rad Sci. April 2016; 2(2): 021002. https://doi.org/10.1115/1.4031842
Download citation file:
- Ris (Zotero)
- Reference Manager