摘要
为丰富我国核反应堆物理中子输运计算手段,对开源蒙特卡罗程序OpenMC进行验证性研究。基于ENDF/B-VII.1核数据库,选取反应堆模拟评价和验证基准(BEAVRS)例题,使用OpenMC程序对BEAVRS压水堆进行全堆芯建模和计算研究。结果表明:5种临界状态下OpenMC程序的临界本征值计算结果最大误差为127 pcm;控制棒价值计算误差在-95~41 pcm之间;U-235相对裂变率计算结果最大相对误差在B13组件为-13.6%。同时,将OpenMC程序计算结果与实测数据及同类软件模拟结果进行比较,结果表明OpenMC程序计算结果与实际情况吻合良好且基本优于同类软件计算结果。因此,开源蒙卡程序OpenMC具有较高的准确性和可靠性,可广泛用于压水堆核电站堆芯模拟研究计算。
In order to enrich the calculation methods of physical neutron transport in nuclear reactors in China,the open sources Monte Carlo program OpenMC is validated.Based on ENDF/B-VII.1 database,the whole core modeling and calculation of BEAVRS(Benchmark Evaluation and Validation Reaction Simulations)pressurized water reactor(PWR)were studied by using open sources Monte Carlo program OpenMC to verify the accuracy of the OpenMC program.The results show that the maximum error of the critical eigenvalues calculated by OpenMC program under five critical states is 127 pcm.The calculation errors of control rod value are between-95 and 41 pcm.The maximum relative error of u-235 relative fission rate calculation is-13.6%for B13 assembly.At the same time,the calculated results of OpenMC program are compared with the measured data and the simulation results of similar software.The results show that the calculated results of OpenMC program agree well with the actual situation and are basically better than those of similar software.Therefore,OpenMC program has high accuracy and reliability,and can be widely used in PWR nuclear power plant core simulation calculation.
作者
郝鹏飞
杨波
秦凯文
张洁茹
刘义保
HAO Pengfei;YANG Bo;QIN Kaiwen;ZHANG Jieru;LIU Yibao(College of Nuclear Science and Engineering,East China University of Technology,Nanchang 330013,China;National Key Laboratory of Nuclear Resources and Environment,East China University of Technology,Nanchang 330013,China)
出处
《能源研究与管理》
2021年第4期80-84,95,共6页
Energy Research and Management
基金
国家自然科学基金(11965001)
江西省教育厅科技计划重点项目(GJJ170428)
核技术应用教育部工程研究中心开放基金(HJSJYB2011-12)。
