基于统一耦合框架的堆芯物理热工耦合程序的开发及验证
作者:
作者单位:

1.中国科学技术大学核科学技术学院;2.中国核动力研究设计院

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通讯作者:

中图分类号:

TL325

基金项目:

核反应堆系统设计技术重点实验室基金(HT-KFKT-02-2020006)


Development and verification of core physical-thermal coupling code based on unified coupling framework
Author:
Affiliation:

1.School of Nuclear Science and Technology, University of Science Technology of China;2.Nuclear Power Institute of China

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    摘要:

    为实现对反应堆多物理多尺度场的综合模拟,基于统一耦合接口理念ICoCo和统一数据传递模型MED库,对中子时空动力学程序CORCA-K和子通道程序CORTH进行了程序封装,并采用supervisor流程控制方案实现了CORCA-K和CORTH之间的耦合. 通过三维轻水堆国际基准NEACRP弹棒算例进行程序验证,数值结果表明,基于统一耦合框架的CORCA-K和CORTH的耦合程序可以实现CORCA-K和CORTH之间的场数据传递与耦合计算,计算结果与CORCA-K已开发的耦合接口计算结果符合地很好,二者与基准结果基本一致.

    Abstract:

    In order to realize the comprehensive simulation of the multi-physics and multi-scale field of the reactor, based on the unified coupling interface concept Interface for Code Coupling (ICoCo) and the unified data transfer model MED library, the space-time neutronics simulation code CORCA-K and the sub-channel code CORTH have been packaged. Furthermore, the coupling between CORCA-K and CORTH was realized by using the supervisor method. The code was verified by the rod ejection cases of 3D LWR core transient benchmark NEACRP. The numerical results show that the CORCA-K and CORTH coupling code based on the unified coupling framework can realize the field data transfer and coupling calculation between CORCA-K and CORTH. The calculation results are in good agreement with those of the CORCA-K coupling interface, and the two results are basically consistent with the benchmark ones.

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引用本文格式: 姜荣,冯文培,陈红丽,强胜龙,李治刚,潘俊杰,张喜林,罗晓. 基于统一耦合框架的堆芯物理热工耦合程序的开发及验证[J]. 四川大学学报: 自然科学版, 2021, 58: 044006.

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历史
  • 收稿日期:2020-12-05
  • 最后修改日期:2021-01-10
  • 录用日期:2021-01-21
  • 在线发布日期: 2021-07-12
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