秦山一期堆本体退役源项估算及辐射场可视化

摘要

According to the actual situation of Qinshan reactor, pin-by-pin neutron transport calculation model for the whole core was set up by Monte Carlo codes, and the reliability of the model was validated.Based on geometric parameters, material parameters, neutron fluence rate distribution of structure parts, and under assumed reactor power operation history, burnup calculation codes are used to calculate the neutron activation products as estimation results of source term after shutdown, and to analyze the 3D radiation field visualized model of source term.The simulation results are consistent with the theoretical analysis.This study is an important fundamental work for the establishment of the decommissioning technology security verification and virtual simulation platform for Qinshan nuclear power plant.%针对我国秦山一期核反应堆实际情况,利用蒙特卡罗程序建立了细化到燃料棒结构的全堆芯pin-by-pin模型进行中子输运计算,并对计算模型的可靠性进行了验证;基于堆本体结构部件的几何参数、材料参数及堆本体中子注量率分布,在假定功率运行史的情况下,利用燃耗计算程序计算了反应堆停堆后的中子活化产物作为堆本体退役源项的估算结果,并对源项产生的三维辐射场剂量分布情况进行了可视化建模与分析,模拟结果与理论分析一致.本研究是下一步建立我国秦山核电厂退役技术安全验证和虚拟仿真平台的关键性基础工作.