基于BEAVRS基准例题的OpenMC程序建模及计算验证

郝鹏飞; 杨波; 秦凯文; 张洁茹; 刘义保

doi:10.16056/j.2096-7705.2021.04.015

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基于BEAVRS基准例题的OpenMC程序建模及计算验证

研究与探讨 | 更新时间：2026-01-19

- 基于BEAVRS基准例题的OpenMC程序建模及计算验证
- OpenMC Program Modeling and Calculation Verification based on BEAVRS Benchmark
- 能源研究与管理 2021年第4期页码：80-84+95
- 作者机构：
  
  1. 东华理工大学核科学与工程学院
  2. 东华理工大学核资源与环境国家重点实验室
- 作者简介：
- 基金信息：
  
  国家自然科学基金（11965001）;江西省教育厅科技计划重点项目（GJJ170428）
- DOI：10.16056/j.2096-7705.2021.04.015
  中图分类号： TL329
- 纸质出版：2021
- 稿件说明：
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郝鹏飞, 杨波, 秦凯文, 等. 基于BEAVRS基准例题的OpenMC程序建模及计算验证[J]. 能源研究与管理, 2021,(4):80-84+95.

郝鹏飞, 杨波, 秦凯文, et al. OpenMC Program Modeling and Calculation Verification based on BEAVRS Benchmark[J]. 2021, (4): 80-84+95.
郝鹏飞, 杨波, 秦凯文, 等. 基于BEAVRS基准例题的OpenMC程序建模及计算验证[J]. 能源研究与管理, 2021,(4):80-84+95. DOI： 10.16056/j.2096-7705.2021.04.015.

郝鹏飞, 杨波, 秦凯文, et al. OpenMC Program Modeling and Calculation Verification based on BEAVRS Benchmark[J]. 2021, (4): 80-84+95. DOI： 10.16056/j.2096-7705.2021.04.015.

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127pcm;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。

Abstract

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.

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