The development of candling module code in module in-vessel degraded analysis code MIDAC and the relevant calculation for CPR1000 during large-break LOCA

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

Research output: Contribution to journalArticlepeer-review

4 Scopus citations

Abstract

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.

Original languageEnglish
Article number021002
JournalJournal of Nuclear Engineering and Radiation Science
Volume2
Issue number2
DOIs
StatePublished - Apr 2016
Externally publishedYes

Funding

This work was finally supported by “Program for Changjiang Scholars and Innovative Research Team in University” (No: IRT1280) and Chinese “National Major Projects” (No: 2011 ZX 06004 008 004).

Keywords

  • CPR1000
  • LOCA
  • MAAP
  • MIDAC
  • Severe accident

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