Assessment of the severe accident code MIDAC based on FROMA, QUENCH-06&16 experiments

Shihao Wu; Yapei Zhang; Dong Wang; Wenxi Tian; Suizheng Qiu; G.H. Su

Nuclear Engineering and Technology (Feb 2022)

Assessment of the severe accident code MIDAC based on FROMA, QUENCH-06&16 experiments

Shihao Wu,
Yapei Zhang,
Dong Wang,
Wenxi Tian,
Suizheng Qiu,
G.H. Su

Affiliations

Shihao Wu: School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
Yapei Zhang: Corresponding author.; School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
Dong Wang: School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
Wenxi Tian: School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
Suizheng Qiu: School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
G.H. Su: School of Nuclear Science and Technology, Shaanxi Engineering Research Center of Advanced Nuclear Energy, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China

Journal volume & issue: Vol. 54, no. 2
pp. 579 – 588

Abstract

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In order to meet the needs of domestic reactor severe accident analysis program, a MIDAC (Module In-vessel Degraded severe accident Analysis Code) is developed and maintained by Xi'an Jiaotong University. As the accuracy of the calculation results of the analysis program is of great significance for the formulation of severe accident mitigation measures, the article select three experiments to evaluate the updated severe accident models of MIDAC. Among them, QUENCH-06 is the international standard No.45, QUENCH-16 is a test for the analysis of air oxidation, and FROMA is an out-of-pile fuel rod melting experiment recently carried out by Xi'an Jiaotong University. The heating and melting model with lumped parameter method and the steam oxidation model with Cathcart-Pawel and Volchek-Zvonarev correlations combination in MIDAC could better meet the needs of severe accident analysis. Although the influence of nitrogen still need to be further improved, the air oxidation model with NUREG still has the ability to provide guiding significance for engineering practice.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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