VVER机组反应堆压力容器中子输运计算程序系统的验证  

A Verification of Neutron Fluence Rate Calculation Code System for VVER Reactor Vessel

作　　者：张亚平[1] 李国健 李锴[1] 王东辉[1] Zhang Yaping;Li Guojian;Li Kai;Wang Donghui(State Nuclear Power Plant Service Company,Shanghai 200233,China)

机构地区：[1]国核电站运行服务技术有限公司,上海200233

出　　处：《核安全》2022年第3期99-106,共8页Nuclear Safety

基　　金：国家压水堆核电重大专项,项目编号:2019ZX06005002。

摘　　要：反应堆压力容器中子注量是评价其辐照损伤状态的基础。本文基于Balakovo-3VVER-1000基准算例提供的数据,采用针对VVER-1000机组开发的堆芯中子源项计算软件,配合DOORS中子输运理论计算程序系统,计算了基准算例中各探测片位置的中子能谱以及各探测片的反应率。通过与基准算例中的参考结果进行比较,验证该中子输运计算程序系统对VVER-1000机组的适用性。结果表明,各探测片的理论计算结果与基准算例中提供的实测结果符合良好,证明新开发的中子源项计算程序可为VVER-1000机组的中子输运理论计算提供准确的中子源项,同时也验证了该中子输运计算程序系统对VVER机组的适用性。Neutron fluence rate is the basis for reactor vessel embrittlement surveillance and assessment.Based on the data provided in Balakovo-3 VVER-1000 benchmark problem,reactor vessel neutron fluence rate calculation was implemented to verify the availability of a neutron fluence rate calculation code system for VVER-1000 reactor.The neutron spectrum and neutron sensor reaction rates were compared during the work.The comparisons show that calculated neutron spectrum and sensor reaction rates agree very well.It proves that the neutron fluence rate calculation code system is reliable to be used in RPV neutron fluence rate calculation for VVER units.

关 键 词：VVER机组 反应堆压力容器 中子注量率 基准算例 程序系统 验证 

分 类 号：TL375[核科学技术—核技术及应用]