基于JMCT秦山核电厂一期反应堆屏蔽计算与分析  

Qinshan-I Reactor Shielding Simulation and Sensitivity Analysis Based on JMCT Monte Carlo Code

作　　者：邓力[1,2] 李瑞 丁谦学 邱有恒 李刚[1] 付元光[2] 史敦福 刘鹏 Deng Li;Li Rui;Ding Qianxue;Qiu Youheng;Li Gang;Fu Yuanguang;Shi Dunfu;Liu Peng(Institute of Applied Physics and Computational Mathematics(IAPCM),Beijing,100094,China;CAEP Software Centre for High Performance Numerical Simulation(CAEP-SCNS),Beijing,100088,China;Shanghai Nuclear Engineering Research and Design Institute Co.Ltd.,Shanghai,200233,China)

机构地区：[1]北京应用物理与计算数学研究所,北京100094 [2]中物院高性能数值模拟软件中心,北京100088 [3]上海核工程研究设计院有限公司,上海200233

出　　处：《核动力工程》2021年第2期173-179,共7页Nuclear Power Engineering

基　　金：能源局重大专项子项(2019ZX06002033);国家自然科学基金(11805017;12001050)。

摘　　要：秦山核电厂一期的运行时间已超过三十年,该反应堆为我国核反应堆建造、运行、延寿乃至退役,提供了丰富的实测数据,为我国新一代反应堆核电厂—华龙一号的设计、建造、运行、维护提供了宝贵的参考数据。本文利用秦山核电厂一期反应堆压力容器的母材段、焊缝段及主管道测试数据,对自主研制的三维中子-光子-电子输运蒙特卡罗软件(JMCT)进行实验验证,模拟结果显示,JMCT软件屏蔽计算具有很高的模拟置信度,计算分辨率超越商业软件1~2个量级。Qinshan-I reactor has been operated for over thirty years. A great amount of data is obtained from the design, building, operation, life-extension and decommission and can provide the valued reference for the design, building, operation and maintenance of the nuclear power plants with new generation reactors, such as HPR1000. In this paper, the test verification for JMCT Monte Carlo particle transport code is carried out based on the test data of Qinshan-I base mental section, weld section and main pipe. The simulated results show that JMCT code is with high precision in radiation shielding simulation. The resolution of JMCT is better than the commercial code for about 1~2 order.

关 键 词：秦山核电厂一期 母材段 焊缝段 主管道 JMCT 

分 类 号：TL334[核科学技术—核技术及应用] O571.51[理学—粒子物理与原子核物理]