摘要
辐射屏蔽计算是核电厂辐射防护设计和审评的重要内容之一。国际屏蔽计算软件对中国实行"出口封锁",制约了我国核电辐射屏蔽审核计算能力,因此,研发了具有自主知识产权的基于蒙特卡罗方法的辐射屏蔽专用蒙特卡罗软件RShieldMC(Radiation Shielding Monte Carlo)。为了验证RShieldMC程序,进行中子注量率计算的准确性和适用性,利用秦山一期反应堆结构与辐照监督管相关参数,通过RShieldMC可视化前处理模块建立辐照监督管屏蔽计算模型,计算秦山一期反应堆辐照监督管堆芯中平面和上焊缝处的中子注量率。RShieldMC程序计算结果与辐照监督管实验测量值以及MCNP(Monte Carlo N-Particle)、JMCT-S(J Monte Carlo Transport)、TORT(Three-dimensional Neutron/Photon Transport)程序计算结果符合较好,验证了RShieldMC软件在中子注量率计算中的可用性及正确性。
[Background] Radiation shielding calculation is one of the important contents in nuclear power plant radiation protection design and evaluation. The international shield calculation software implements the "export blockade" on China, which limits the calculation ability of radiation shielding audit.[Purpose] This study aims to develop a dedicate radiation shielding software and verify its validity and correctness in neutron flux calculation.[Methods] First of all, based on Monte-Carlo method, a radiation shielding software, named RShieldMC, was developed. Then the measurement data of Qinshan radiation monitoring tube was used for the code verification. The Qinshan No.1 nuclear plant was modeled via visual modeling software of RShieldMC. The neutron flux of the midplane and upper weld in the radiation monitoring tube were calculated by using RShieldMC code.[Results] The calculated results of RShieldMC are in good consistency with the measured values of the radiation monitoring tube test. In addition, the results were also compared with that of MCNP(Monte Carlo N-Particle), JMCT-S(J Monte Carlo transport)and TORT(Three-dimensional Neutron/Photon Transport)programs.[Conclusion] The consistency of the experimental results demonstrates the applicability of RShieldMC in the calculation of neutron flux in PWR.
作者
韩静茹
石生春
徐翀
王宏凯
左嘉旭
靖剑平
HAN Jingru;SHI Shengchun;XU Chong;WANG Hongkai;ZUO Jiaxu;JING Jianping(Nuclear and Radiation Safety Center,Beijing 100082,China)
出处
《核技术》
CAS
CSCD
北大核心
2019年第3期64-68,共5页
Nuclear Techniques
基金
国家自然科学基金(No.11705066)资助~~