期刊文献+

VVER机组堆芯中子源项计算程序的开发和验证

Development and Validation of Neutron Source Calculation Code for the Reactor Core of VVER
下载PDF
导出
摘要 堆芯中子源项计算是反应堆压力容器中子注量理论计算最关键步骤之一。采用Fortran语言,开发了堆芯中子源项计算程序SCON,并基于Balakovo-3VVER-1000基准算例所提供数据,结合中子输运理论计算DOORS软件系统,对SCON开展了验证。结果表明,计算得到的各探测片反应率与基准算例中所提供的实测结果符合良好,证明SCON程序可为六边形燃料组件机组中子输运理论计算提供准确的中子源项,同时也证明本文采用的中子注量率计算软件系统是适用于VVER机组的。 Calculation of reactor core neutron source is one the most important procedures of neutron fluence rate calculation for the reactor vessel. A neutron source calculation code SCON was developed with Fortran for VVER with hexagonal fuel assemblies. Balakovo-3VVER-1000 benchmark problem and the neutron transport calculation code system DOORS were used to validate SCON. The results showed that the calculated results agree well with the reference results. It proves that the SCON code can provide accurate neutron source for the neutron transport calculation of the units with hexagonal fuel assemblies. It also proves that the neutron fluence rate calculation code system applies to the RPV neutron fluence calculation for VVER units.
作者 张亚平 张萌 杨兴旺 王东辉 钟志民 ZHANG Yaping;ZHANG Meng;YANG Xingwang;WANG Donghui;ZHONG Zhimin(State Nuclear Power Plant Service Company,Shanghai200233,China;Jiangsu Nuclear Power Company Limited,Lianyungang of Jiangsu Prov.222000,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2022年第6期1285-1290,共6页 Nuclear Science and Engineering
基金 国家压水堆核电重大专项(2019ZX06005002) 江苏核电有限公司内部课题(JNPC-KY-201864)。
关键词 VVER机组 反应堆压力容器 中子注量率 堆芯中子源项 程序开发 软件验证 VVER reactor Reactor vessel Neutron fluence rate Code development Code validation
  • 相关文献

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部