基于RG 1.183的先进小堆选址源项模型初步研究

在《用于评估核动力反应堆设计基准事故的替代放射性源项》RG 1.183所述的假想事故场景情况下,考虑目前大多数的先进小型压水堆地上-地下布置的设计特点,对传统大型压水堆选址源项计算模型做了改进:在原安全壳内放射性物质守恒方程的基础上,考虑辅助厂房的阻滞作用,建立辅助厂房内放射性物质守恒方程。并以某先进小型反应堆核电厂为例,利用新模型计算了代表核素的释放,与现有模型进行了对比。

Preliminary study on source term model for advanced SMR siting based on RG 1.183

Based on the scenarios of hypothetical accidents described in RG 1. 183 "Alternative radiological source terms for evaluating design basis accidents at nuclear power reactors",considering the design features of most of the current advanced small modular reactor( SMR) on & under ground layouts,the calculation model of the source term of large pressurized water reactor was improved: based on the radioactive conservation equation in the containment, considering the obstacles and retention of the auxiliary building, the radioactive conservation equation in the auxiliary building was established. Taking an advanced small modular reactor nuclear power plant as an example,the radioactive release of the representative nuclides was calculated using the new model and compared with the existing model.