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ORIGINAL RESEARCH article

Front. Energy Res.
Sec. Nuclear Energy
Volume 12 - 2024 | doi: 10.3389/fenrg.2024.1400805

Development and validation of ARSAC-CORTH coupling code based on a generic coupling architecture

Provisionally accepted
Xiaoyu Wang Xiaoyu Wang 1Zhifang Qiu Zhifang Qiu 1*Shinian Peng Shinian Peng 1*Jian Deng Jian Deng 1*Wei Zeng Wei Zeng 1*Luguo Liu Luguo Liu 1*Xilin Zhang Xilin Zhang 1*Xue Zhang Xue Zhang 1Yunfeng Xia Yunfeng Xia 2*Mingjun Wang Mingjun Wang 2*
  • 1 Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,, Chengdu, China, China
  • 2 Xi'an Jiaotong University, Xi'an, Shaanxi Province, China

The final, formatted version of the article will be published soon.

    Reactor thermal-hydraulic codes can be categorized into system codes, sub-channel codes and CFD (computational fluid dynamics) codes according to the spatial discretization and simplification methods. As a traditional reactor system safety analysis code, system code is able to analyze the overall performance of the reactor quickly, while it cannot capture the mixing effects between coolant channels in the core accurately. The sub-channel code is currently the most suitable code for core analysis, with higher fidelity than system code and less computation resources than CFD code. To perform analysis of coupling effects between thermal-hydraulics characteristics of the reactor system and those of core, the in-house system code ASRAC and the in-house sub-channel code CORTH are coupled based on a generic coupling architecture. This generic coupling architecture comprises the generic coupling interface concept ICoCo (Interface for Code Coupling) and the generic data exchange model MED (Model for Exchanging field Data). In order to evaluate the accuracy and capability of the coupling code, the LOFT experiment case is chosen and analyzed. According to the validation results, compared with ASRAC code standalone, the ARSAC-CORTH coupling code is able to better analyze the coupling effects of loop system and core, meanwhile capturing the coolant mixing between coolant channels.

    Keywords: System code, Sub-channel code, Code coupling, Generic coupling architecture, Code validation

    Received: 14 Mar 2024; Accepted: 28 Jun 2024.

    Copyright: © 2024 Wang, Qiu, Peng, Deng, Zeng, Liu, Zhang, Zhang, Xia and Wang. This is an open-access article distributed under the terms of the Creative Commons Attribution License (CC BY). The use, distribution or reproduction in other forums is permitted, provided the original author(s) or licensor are credited and that the original publication in this journal is cited, in accordance with accepted academic practice. No use, distribution or reproduction is permitted which does not comply with these terms.

    * Correspondence:
    Zhifang Qiu, Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,, Chengdu, China, China
    Shinian Peng, Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,, Chengdu, China, China
    Jian Deng, Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,, Chengdu, China, China
    Wei Zeng, Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,, Chengdu, China, China
    Luguo Liu, Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,, Chengdu, China, China
    Xilin Zhang, Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China,, Chengdu, China, China
    Yunfeng Xia, Xi'an Jiaotong University, Xi'an, 710049, Shaanxi Province, China
    Mingjun Wang, Xi'an Jiaotong University, Xi'an, 710049, Shaanxi Province, China

    Disclaimer: All claims expressed in this article are solely those of the authors and do not necessarily represent those of their affiliated organizations, or those of the publisher, the editors and the reviewers. Any product that may be evaluated in this article or claim that may be made by its manufacturer is not guaranteed or endorsed by the publisher.