MC-MC耦合计算方法在核电厂中子屏蔽设计中的应用

中子屏蔽精细化设计是三代堆型核电厂区别于二代堆的主要辐射防护设计特征之一,其设计优劣直接影响了辐射场内设备寿命及功率运行期间可能进入的工作人员的辐射安全。为了精确、快速、有效解决大尺度复杂厂房中子屏蔽计算难题,提出了将MC-MC耦合计算应用于解决核电厂大型复杂计算模型的中子屏蔽设计方法。通过与欧洲第三代压水堆技术方案(CEPR)设计结果对比表明,计算结果偏差小于15%,满足工程屏蔽设计误差要求,证明该方法的正确性与可行性。该方法已应用于国内某三代堆型核电厂反应堆厂房中子屏蔽设计。

Application of MC-MC coupled method in neutron shielding analysis of NPP

The detailed neutron shielding design is one of the main radiation protection design features of the third generation reactor, which will directly affect equipment life located in radiation field and the radiation safety of the workers entering the plant during the power operation. So far, there is no effective neutron calculation method that can meet the engineering design requirements in China due to excessively time-consuming and poor accuracy caused by large scale and complex structure. The MC-MC coupling calculation method is proposed to make the large-scale complex neutron shielding calculation accurately, quickly and effectively. The difference between the results obtained by this method and those obtained by CEPR design shows that this method is reliable in engineering design. This method has been used in a 3rd generation PWR in China.