Platform development for multi-physics coupling and uncertainty analysis based on a unified framework

Guan-Hua Qian; Ren Li; Tao Yang; Xu Wang; Peng-Cheng Zhao; Ya-Nan Zhao; Tao Yu

Nuclear Engineering and Technology (May 2023)

Platform development for multi-physics coupling and uncertainty analysis based on a unified framework

Guan-Hua Qian,
Ren Li,
Tao Yang,
Xu Wang,
Peng-Cheng Zhao,
Ya-Nan Zhao,
Tao Yu

Affiliations

Guan-Hua Qian: School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, China
Ren Li: College of Nuclear Science and Technology, Harbin Engineering University, Harbin, Heilongjiang, 150001, China
Tao Yang: School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, China
Xu Wang: School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, China
Peng-Cheng Zhao: School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, China
Ya-Nan Zhao: School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, China; Corresponding author. School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China.
Tao Yu: School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China; Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, Hunan, 421001, China; Corresponding author. School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China.

Journal volume & issue: Vol. 55, no. 5
pp. 1791 – 1801

Abstract

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The multi-physics coupled methodologies that have been widely used to analyze the complex process occurring in nuclear reactors have also been used to the R&D of numerical reactors. The advancement in the field of computer technology has helped in the development of these methodologies. Herein, we report the integration of ADPRES code and RELAP5 code into the SALOME-ICoCo framework to form a multi-physics coupling platform. The platform exploits the supervisor architecture, serial mode, mesh one-to-one correspondence and explicit coupling methods during analysis, and the uncertainty analysis tool URANIE was used. The correctness of the platform was verified through the NEACRP-L-335 benchmark. The results obtained were in accordance with the reference values. The platform could be used to accurately determine the power peak. In addition, design margins could be gained post uncertainty analysis. The initial power, inlet coolant temperature and the mass flow of assembly property significantly influence reactor safety during the rod ejections accident (REA).

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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