核动力工程2024,Vol.45Issue(4) :17-23.DOI:10.13832/j.jnpe.2024.04.0017

PCM核设计软件包全堆芯计算模块的验证

Verification of PCM Nuclear Design Code for Whole Core Calculations

陆高奇 丁铭 兰兵 潘昕怿 李春 王超 马云帆
核动力工程2024,Vol.45Issue(4) :17-23.DOI:10.13832/j.jnpe.2024.04.0017

PCM核设计软件包全堆芯计算模块的验证

Verification of PCM Nuclear Design Code for Whole Core Calculations

陆高奇 1丁铭 1兰兵 2潘昕怿 2李春 2王超 3马云帆3
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作者信息

  • 1. 哈尔滨工程大学黑龙江省核动力装置性能与设备重点实验室,哈尔滨,150001
  • 2. 生态环境部核与辐射安全中心,北京,100082
  • 3. 中广核研究院有限公司,广东深圳,518031
  • 折叠

摘要

PCM软件包是中广核研究院有限公司自主研发的核设计软件包,包含组件截面计算软件PINE和三维堆芯核设计软件COCO.为了验证PCM软件包的全堆芯计算能力及其准确性,本文基于自制全堆芯例题以及国际通用的BIBLIS、IAEA、LRA等全堆芯基准题对PCM软件包"组件-堆芯"两步法和COCO软件的堆芯计算功能进行了验证.在轻水堆堆芯基准题的计算中,所有算例的有效增殖系数keff平均偏差为6.4pcm(1pcm=10-5),最大偏差仅为28.2pcm,且所有算例中堆芯燃料组件归一化功率分布偏差的绝对值不超过1%.验证结果表明PCM软件包的全堆芯计算功能有较高计算精度,整体计算精度能够满足工程需求.

Abstract

PCM software package,independently developed by China Nuclear Power Technology Research Institute Co.Ltd.,is a nuclear design code consisting of assembly section calculation code PINE and 3D core design code COCO.To validate the whole core calculation capability and accuracy of the PCM nuclear design code,this study conducted verification using internationally recognized benchmark problems such as BIBLIS,IAEA,and LRA,as well as a self-made whole-core problem for the COCO code and the"assembly-core"two-step method within the PCM nuclear design code.The verification results indicated that in the calculations of the light-water reactor core benchmark problems,the average error of the effective multiplication factor(keff)for all cases was 6.4pcm,with a maximum error of only 28.2pcm.In all the cases,the deviation of the normalized power distribution of the core fuel assemblies did not exceed 1%.The verification results show that the whole core calculation function of the PCM nuclear design code exhibits high computational accuracy,and the overall calculation accuracy can meet the engineering requirements.

关键词

堆芯核设计/堆芯基准题/PCM软件包

Key words

Core nuclear design/Core benchmark/PCM software package

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基金项目

国家自然科学基金项目(11405036)

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11
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