核动力工程2024,Vol.45Issue(5) :115-120.DOI:10.13832/j.jnpe.2024.05.0115

CRANE/EAGLE高保真多物理耦合软件系统的初步工程验证

Preliminary Engineering Validation of the High-fidelity Multi-Physical Coupling Code CRANE/EAGLE

陈国华 冯进军 陈超 蒋校丰 王涛
核动力工程2024,Vol.45Issue(5) :115-120.DOI:10.13832/j.jnpe.2024.05.0115

CRANE/EAGLE高保真多物理耦合软件系统的初步工程验证

Preliminary Engineering Validation of the High-fidelity Multi-Physical Coupling Code CRANE/EAGLE

陈国华 1冯进军 2陈超 1蒋校丰 1王涛1
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作者信息

  • 1. 上海核星核电科技有限公司,上海,201103
  • 2. 生态环境部核与辐射安全中心,北京,100082
  • 折叠

摘要

基于采用图形处理单元(GPU)加速的数值反应堆物理程序CRANE和子通道热工水力程序EAGLE,通过源代码层面的直接联合编译形成了一套CRANE/EAGLE高保真多物理耦合软件系统.目前已经对CRANE/EAGLE软件系统开展了大量的验证和确认工作,本文主要介绍对田湾核电站5号机组(M310机组)首循环和田湾核电站4号机组(VVER-1000机组)首循环的验证结果.针对这两个机组的首循环,开展了启动物理参数的计算和以天为单位的运行历史跟踪模拟.计算结果表明,CRANE/EAGLE软件系统不仅具备非常高的计算精度,而且能在小型多GPU计算平台上以分钟级别的时间完成商用压水堆单个状态点的多物理耦合计算.本文所验证的CRANE/EAGLE软件系统已初步具备了工程应用价值.

Abstract

Based on the numerical reactor physical code CRANE and sub-channel thermal hydraulic code EAGLE accelerated by GPU,a set of CRANE/EAGLE high fidelity multi-physical coupling software system was developed through direct joint compilation at the source code level.A large amount of verification and validation work has been carried out on the CRANE/EAGLE system.This paper mainly introduces the verification results of the first cycle of Tianwan Unit 5(M310 reactor)and Unit 4(VVER-1000 reactor).According to the first cycle of these two units,the calculation of starting physical parameters and the tracking simulation of operation history in days are carried out.The numerical results show that the CRANE/EAGLE code system not only has high calculation accuracy,but also can complete the multi-physics coupling calculation of a single state point of a commercial pressurized water reactor in minutes on a small multi-GPU computing platform.The CRANE/EAGLE software system verified in this paper has preliminary engineering application value.

关键词

CRANE/EAGLE/图形处理单元(GPU)/高保真/多物理耦合/工程验证

Key words

CRANE/EAGLE/GPU/High-fidelity/Multi-physics/Engineering validation

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出版年

2024
核动力工程
中国核动力研究设计院

核动力工程

CSTPCDCSCD北大核心
影响因子:0.3
ISSN:0258-0926
参考文献量9
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