基于BEAVRS2.0三维堆芯仿真建模验证分析
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摘要
针对最新发布的BEAVRS2.0基准题,采用多群二维输运理论进行燃耗计算,得到离散工况下少群常数并进行截面拟合处理,将先进节块法应用于求解中子扩散方程,建立三维堆芯节块程序SimOR仿真计算模型;选取不同运行工况进行组件均匀化计算、堆芯临界计算,并建立堆芯临界燃耗分析模型,并与BEAVRS2.0基准测量解、nTRACER等程序参考解比对,其计算结果吻合很好,验证了仿真模型建立的正确性与程序计算的精准性,可以广泛应用于核电仿真计算研究,同时为压水堆燃料管理燃料组件计算、堆芯扩散-燃耗计算提供数据依据及方案参考。
[Background] Based on the latest release of benchmark for evaluation and validation of reactor simulations(BEAVRS), verification of three-dimensional core simulation is one of important issues. [Purpose] This study aims to verify simulation modeling of three-dimensional core in coordinate with BEAVRS version 2.0 and establish corresponding burnup analysis model. [Methods] First of all, 2 D transport theory with multi-group was used to calculate the fuel burnup, and few-group constant of discrete state points for calculation of nuclear cross sections fitting model. Then, the advanced nodal method was used to solve the neutron diffusion equation, and establish the 3 D core nodal code SimOR simulation model. Finaly, various operating conditions were selected to carry out component homogenization calculation and core critical calculation. [Results] The calculation results are in good agreement with the measured values of BEAVRS benchmark and the reference results of nTRACER code,which verifies the correctness of the simulation model and the accuracy of the program calculation. [Conclusion]This study provides data basis and scheme reference for the calculation of fuel management components and core diffusion-burnup calculation of PWR.
[Background] Based on the latest release of benchmark for evaluation and validation of reactor simulations(BEAVRS), verification of three-dimensional core simulation is one of important issues. [Purpose] This study aims to verify simulation modeling of three-dimensional core in coordinate with BEAVRS version 2.0 and establish corresponding burnup analysis model. [Methods] First of all, 2 D transport theory with multi-group was used to calculate the fuel burnup, and few-group constant of discrete state points for calculation of nuclear cross sections fitting model. Then, the advanced nodal method was used to solve the neutron diffusion equation, and establish the 3 D core nodal code SimOR simulation model. Finaly, various operating conditions were selected to carry out component homogenization calculation and core critical calculation. [Results] The calculation results are in good agreement with the measured values of BEAVRS benchmark and the reference results of nTRACER code,which verifies the correctness of the simulation model and the accuracy of the program calculation. [Conclusion]This study provides data basis and scheme reference for the calculation of fuel management components and core diffusion-burnup calculation of PWR.
引文
1 Horelik N,Herman B,Ellis M,et al.Benchmark for evaluation and validation of reactor simulation(BEAVRS)[R].Version 2.0.1.Massachusetts Institute of Technology:MIT Computational Reactor Physics Group,2017.
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5 Min Ryu,Yeon Sang Jung,Hyun Ho Cho,et al.Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code[J].Journal of Nuclear Science and Technology,2015,52:7?8,961?969.DOI:10.1080/00223131.2015.1038664.
6 Wang Z Y,Wu B,Hao L J,et al.Validation of SuperMCwith BEAVRS benchmark at hot zero power condition[J].Annals of Nuclear Energy,2018,111:709?714.DOI:10.1016/j.anucene.2017.09.045.
7 Wang K,Liu S C,Li Z G,et al.Analysis of BEAVRS twocycle benchmark using RMC based on full core detailed model[J].Progress in Nuclear Energy,2017,98:301?312DOI:10.1016/j.pnucene.2017.04.009.
8 Liu S C,Liang J G,Wu Q,et al.BEAVRS full core burnup calculation in hot full power condition by RMCcode[J].Annals of Nuclear Energy,2017,101:434?446.
9 Li Z,Cao L Z,Wu H C,et al.Sensitivity analysis for the weighting factor in the least-square method for the PWRon-line power-distribution monitoring[J].Annals of Nuclear Energy,2017,109:675?683.DOI:10.1016/j.anucene.2017.06.008.
10 Jaakko Lepp?nen,Riku Mattila.Validation of the SerpentARES code sequence using the MIT BEAVRS benchmark-HFP conditions and fuel cycle 1 simulations[J].Annals of Nuclear Energy,2016,96:324?331.DOI:10.1016/j anucene.2014.02.014.
2谢明亮,于雷,陈玉清.AP1000核反应堆控制棒价值特性的MC模拟[J].兵器装备工程学报,2016,37(3):121?125.DOI:10.11809/scbgxb2016.03.029.XIE Mingliang,YU Lei,CHEN Yuqing.Analysis of control rod worth features of MC simulation in AP1000reactor[J].Journal of Ordnance Equipment Engineering,2016,37(3):121?125.DOI:10.11809/scbgxb2016.03.029.
3谢明亮,陈玉清,于雷,等.基于WIMS格式多群核数据制作过程的优化分析[J].核技术,2015,38(11):110502.DOI:10.11889/j.0253-3219.2015.hjs.38.110502.XIE Mingliang,CHEN Yuqing,YU Lei,et al.Optimization analysis of the production process based on WIMS format multigroup nuclear data[J].Nuclear Techniques,2015,38(11):110502.DOI:10.11889/j.0253-3219.2015.hjs.38.110502.
4廖承奎,谢仲生.非线性迭代半解析节块方法在压水堆燃料管理计算中的应用[J].核科学与工程,2003,23(1):14?19.DOI:10.3321/j.issn:0258-0918.2003.01.003.LIAO Chengkui,XIE Zhongsheng.Application of nonlinear iteration semi-analytical nodal method in the PER fuel management calculation[J].Chinese Journal of Nuclear Science and Engineering,2003,23(1):14?19.DOI:10.3321/j.issn:0258-0918.2003.01.003.
5 Min Ryu,Yeon Sang Jung,Hyun Ho Cho,et al.Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code[J].Journal of Nuclear Science and Technology,2015,52:7?8,961?969.DOI:10.1080/00223131.2015.1038664.
6 Wang Z Y,Wu B,Hao L J,et al.Validation of SuperMCwith BEAVRS benchmark at hot zero power condition[J].Annals of Nuclear Energy,2018,111:709?714.DOI:10.1016/j.anucene.2017.09.045.
7 Wang K,Liu S C,Li Z G,et al.Analysis of BEAVRS twocycle benchmark using RMC based on full core detailed model[J].Progress in Nuclear Energy,2017,98:301?312DOI:10.1016/j.pnucene.2017.04.009.
8 Liu S C,Liang J G,Wu Q,et al.BEAVRS full core burnup calculation in hot full power condition by RMCcode[J].Annals of Nuclear Energy,2017,101:434?446.
9 Li Z,Cao L Z,Wu H C,et al.Sensitivity analysis for the weighting factor in the least-square method for the PWRon-line power-distribution monitoring[J].Annals of Nuclear Energy,2017,109:675?683.DOI:10.1016/j.anucene.2017.06.008.
10 Jaakko Lepp?nen,Riku Mattila.Validation of the SerpentARES code sequence using the MIT BEAVRS benchmark-HFP conditions and fuel cycle 1 simulations[J].Annals of Nuclear Energy,2016,96:324?331.DOI:10.1016/j anucene.2014.02.014.