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Research Papers

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

[+] Author and Article Information
Jun Wang

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

Yuqiao Fan, Yapei Zhang, Xinghe Ni, Wenxi Tian, Suizheng Qiu

State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology,
Xi’an Jiaotong University,
Xi’an 710049, China

Michael L. Corradini

College of Engineering,
University of Wisconsin-Madison,
Madison, WI 53706

Guanghui Su

State Key Laboratory of Multiphase Flow in Power Engineering, Department of Nuclear Science and Technology,
Xi’an Jiaotong University,
Xi’an 710049, China
e-mail: ghsu@mail.xjtu.edu.cn

1Corresponding author.

Manuscript received January 27, 2015; final manuscript received October 17, 2015; published online February 29, 2016. Assoc. Editor: Xu Cheng.

ASME J of Nuclear Rad Sci 2(2), 021002 (Feb 29, 2016) (10 pages) Paper No: NERS-15-1009; doi: 10.1115/1.4031842 History: Received January 27, 2015; Accepted October 17, 2015

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.

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Figures

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Fig. 1

Two mechanisms for flowing downward: (a) outer-membrane flow and (b) internal tubular flow

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Fig. 2

Nodalization of primary loop

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Fig. 3

Nodalization of reactor core

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Fig. 4

Results of MIDAC in different break sizes

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Fig. 5

Comparison of MIDAC and MAAP4 when break size was 40 cm

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Fig. 6

Comparison of MIDAC and MAAP4 when break size was 30 cm

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Fig. 7

Comparison of MIDAC and MAAP4 when break size was 20 cm

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