超级蒙特卡罗核计算仿真软件系统SuperMC
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摘要
蒙特卡罗方法对于复杂核系统的模拟具有明显优势,然而在实际工程应用中存在巨大的挑战,如复杂结构与材料分布精准建模难度大、计算收敛速度慢、海量数据难以及时有效分析等。超级蒙特卡罗核计算仿真软件系统SuperMC设计为支持以辐射输运为核心,包含燃耗、辐射源项/剂量/生物危害、材料活化与嬗变等的综合中子学计算,支持热工水力学、结构力学、化学、生物学等多物理耦合模拟。SuperMC目前已发展了精准建模、高效计算、四维可视化等关键技术,通过2 000余个国际基准模型及实验的验证与确认,在反应堆工程等方面获得广泛应用,本文对其发展概况进行介绍。
Monte Carlo method has distinct advantages in simulating complicated nuclear systems.However,great challenges to current MC methods and codes prevent its application in engineering projects,such as difficulties in the accurate modeling of complex geometries and material distribution,slow convergence of calculation,prompt and effective analysis of massive data.Super Monte Carlo Simulation Program for Nuclear and Radiation Process(SuperMC) is designed to perform the comprehensive neutronics calculation,taking the radiation transport as the core and including the depletion,radiation source term/dose/biohazard,material activation and transmutation,etc.It supports the multi-physics coupling calculation including thermo-hydraulics,structural mechanics,chemistry,biology,etc.Key techniques including automatic and accurate modeling,high efficient calculation,4D visualization were developed and more than2000 international benchmark models and experiments were used to verify and validate SuperMC.SuperMC has been widely used in reactor engineering projects and etc.In this paper,the overview of SuperMC development was introduced.
Monte Carlo method has distinct advantages in simulating complicated nuclear systems.However,great challenges to current MC methods and codes prevent its application in engineering projects,such as difficulties in the accurate modeling of complex geometries and material distribution,slow convergence of calculation,prompt and effective analysis of massive data.Super Monte Carlo Simulation Program for Nuclear and Radiation Process(SuperMC) is designed to perform the comprehensive neutronics calculation,taking the radiation transport as the core and including the depletion,radiation source term/dose/biohazard,material activation and transmutation,etc.It supports the multi-physics coupling calculation including thermo-hydraulics,structural mechanics,chemistry,biology,etc.Key techniques including automatic and accurate modeling,high efficient calculation,4D visualization were developed and more than2000 international benchmark models and experiments were used to verify and validate SuperMC.SuperMC has been widely used in reactor engineering projects and etc.In this paper,the overview of SuperMC development was introduced.
引文
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[19]J.Zou,Z.He,Q.Zeng,et al.Development and Testing of Multigroup Library with Correction of Selfshielding Effects in Fusion-Fission Hybrid Reactor[J].Fusion Engineering and Design,2010,85(7-9):1587-1590.
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[21]S.Yu,M.Cheng,J.Song,et al.Convex-based Void Filling Method for CAD-based Monte Carlo Geometry Modeling[J].Annals of Nuclear Energy,2015,85:380-385.
[22]B.Wu,Z.Chen,J.Song,et al.Advanced Geometry Navigation Methods without Cavity Representation for Fusion Reactors[R].MC SNA MC 2015,Nashville,April 19-23,2015.
[23]P.Long,Q.Zeng,T.He,et al.Development of a Geometry-Coupled Visual Analysis System for MCNP[J].Progress in Nuclear Science and Technology,2011,2:280-283.
[24]Z.Chen,J.Song,H.Zheng,et al.Optimal Spatial Subdivision Method for Improving Geometry Navigation Performance in Monte Carlo Particle Transport Simulation[J].Annals of Nuclear Energy,2015,76:479.
[25]Z.Chen,J.Song,G.Sun,et al.Geometry Navigation Acceleration based on Automatic Neighbour Search and Bounding Box in Monte Carlo Simulation[R].Proceeding of PHYSOR2014-The Role of Reactor Physics Toward a Sustainable Future,Nara,Japan 2014.
[26]Y.Wu,G.Song,R.Cao,et al.Development of Accurate/Advanced Radiotherapy Treatment Planning and Quality Assurance System(ARTS)[J].Chinese Physics C(HEP&NP),2008,32(Suppl.Ⅱ):177-182.
[27]Y.Yan,J.Song,H.Zheng,et al.On-the-fly Diagnostic Source Convergence Acceleration Methodology for Monte Carlo Criticality Calculation[R].Proceeding of 23th International Conference on Nuclear Engineering,May17-21,Chiba,Japan 2015.
[28]N.Horelik,B.Herman.Benchmark for Evaluation and Validation of Reactor Simulations[R].MIT,2013.
[29]N.Horelik,B.Herman,B.Forget,et al.MIT BEAVRS:Benchmark for Evaluation and Validation of Reactor Simulations[R].M&C 2013,May 5-9,Sun Valley,USA(2013).
[30]P.Wilson,R.Feder,U.Fischer,et al.State-of-theart 3-D Radiation Transport Methods for Fusion Energy Systems[J].Fusion Engineering and Design,2008,83:824-833.
[31]J.Song,G.Sun,Z.Chen,et al.Benchmarking of CAD-based SuperMC with ITER Benchmark Model[J].Fusion Engineering and Design,2014,89(11):2499-2503.
[32]Q.Zeng,L.Lu,A.Ding,et al.Update of ITER 3D Basic Neutronics Model with MCAM[J].Fusion Engineering and Design,2006,81(23-24):2773-2778.
[33]Q.Zeng,G.Wang,T.Dang,et al.Use of MCAM in Creating 3D Neutronics Model for ITER Buiiding[J].Fusion Engineering and Design,2012,87:1273-1276.
[34]D.Ying,Q.Zeng,Y.Qiu,et al.Assessment of Radiation Maps during Activated Divertor Moving in the ITER Building[J].Fusion Engineering and Design,2011,86(9-11):2087-2091.
[35]T Dang,D Ying,Q Yang,et al.First Neutronics Analysis for ITER Bio-shield Equatorial Port Plug[J].Fusion Engineering and Design.2012,87:1447-1452.
[36]Q.Yang,T.Dang,D.Ying,et al.Activation Analysis of Coolant Water in ITER Blanket and Divertor[J].Fusion Engineering and Design,2012,87(7-8),1310-1314.
[37]S.Yu,Q.Yang,C.Chen,etc.Shielding Design for Activated First Wall Transferring in ITER Hot Cell Building[J].Journal of Fusion Energy.2015,34(4):887-894.
[38]Q.Yang,B.Li,C.Chen,etc.Shielding Analysis for ITER Equatorial Port Cell During Blanket Replacement[J].Journal of Fusion Energy,2015,34(4):875-881.
[39]S.Zheng,E.Polunovskiy.Nuclear Heat of TF Inboard Legs with Fine Structures of Inboard Blanket[R].INAR-001,(2007).
[40]A.Turner,R.Pampin,M.Loughlin,et al.Nuclear Analysis and Shielding Optimisation in Support of the ITER In-Vessel Viewing System Design[J].Fusion Engineering and Design,2014,89:1949-1953.
[41]R.Pampina,S.Zheng,S.Lilley,et al.Activation Analyses Updating the ITER Radioactive Waste Assessment[J].Fusion Engineering and Design.2012,87:1230-1234.
[42]吴宜灿,柏云清,宋勇,等.中国铅基研究反应堆概念设计研究[J].核科学与工程,2014,34(2):56-63.
[43]Y.Wu,Y.Bai,Y.Song,et al.Development Strategy and Conceptual Design of China Lead-based Research Reactor[J].Annals of Nuclear Energy,2016,87:511-516.
[2]D.Griesheimer,D.Gill,B.Nease,et al.MC21v.6.0-A Continuous-Energy Monte Carlo Particle Transport Code with Integrated Reactor Feedback Capabilities[R].Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013(SNA+MC 2013),La Cite des Sciences et de l'Industrie,Paris,France 2013.
[3]Y.Wu,G.Xu.The Need for Further Development of CAD/MCNP Interface Codes[J]Transactions American Nuclear Society,2007,96:392-394.
[4]P.J.Turinsky.Advances in Multi-physics and High Performance Computing in Support of Nuclear Reactor Power Systems Modeling and Simulation[J],Nuclear Engineering and Technology,2012,44(2):103-112.
[5]F.Brown.Recent Advances and Future Prospects for Monte Carlo[J],Progress in Nuclear Science and Technology,2011,2:1-4.
[6]G.Palmiotti,J.Cahalan,P.Pfeiffer,et al.Requirements for Advanced Simulation of Nuclear Reactor and Chemical Separations Plants[R].Argonne National Laboratory,(2005).
[7]Y Wu,J Song,H Zheng,et al.CAD-based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC[J].Annuals of Nuclear Energy,2015,82:161-168.
[8]Y Wu and FDS Team.CAD-based Interface Programs for Fusion Neutron Transport Simulation[J].Fusion Engineering and Design,2009,84:1987-1992.
[9]吴宜灿,李莹,卢磊,等.蒙特卡罗粒子输运计算自动建模程序系统的研究与发展[J].核科学与工程,2006,26(1):20-27.
[10]G Wang,J Xiong,P Long,et al.Progress and Applications of MCAM:Monte Carlo Automatic Modeling Program for Particle Transport Simulation[J].Progress in Nuclear Science and Technology,2011,2,821-825.
[11]吴宜灿,俞盛朋,程梦云等.多物理耦合分析自动建模软件SuperMC/MCAM5.2设计与实现[J].原子能科学技术,2015,49(增刊):23-28.
[12]H.Hu,Y.Wu,M.Chen,et al.Benchmarking of SNAM with the ITER 3D Model[J].Fusion Engineering and Design,2007,82(15-24):2867-2871.
[13]J.Zhang,L.Hu,Q.Zeng,et al.Development and Application of MC-SN Coupled Auto-modeling Tool RCAM1.0[J].Fusion Engineering and Design,2011,86(9-11):2783-2786.
[14]M.Chen,S.Huang,J.Li,et al.Progress of HUMOP:Human Automatic Modeling Program[J].Transactions of the American Nuclear Society,2011,104:648-649.
[15]Y.Luo,P.Long,G.Wu,et al.SVIP-N 1.0:an Integrated Visualization Platform for Neutronics Analysis[J].Fusion Engineering and Design,2010,85(7-9):1527-1530.
[16]Y.Wu,T.He,L.Hu,et al.Development of Virtual Reality-Based Simulation System for Nuclear and Radiation Safety[J].Atomic Energy Science and Technology,2015,29:77-85.
[17]程梦云,王文,范言昌等.基于中国辐射虚拟人RadHUMAN的中子剂量转换系数[J].原子能科学技术,2015,49增刊:65-72.
[18]D.Xu,Z.He,J.Z,et al.Production and Testing of HENDL-2.1/CG Coarse-group Cross-section Library Based on ENDF/B-VII.0[J].Fusion Engineering and Design,2010,85(10-12),2105-2110.
[19]J.Zou,Z.He,Q.Zeng,et al.Development and Testing of Multigroup Library with Correction of Selfshielding Effects in Fusion-Fission Hybrid Reactor[J].Fusion Engineering and Design,2010,85(7-9):1587-1590.
[20]罗月童,樊晓菁,俞盛朋等.基于面壳封闭的B-Rep至CSG转换算法[J].计算机辅助设计与图形学学报,2014,10:1673-1680.
[21]S.Yu,M.Cheng,J.Song,et al.Convex-based Void Filling Method for CAD-based Monte Carlo Geometry Modeling[J].Annals of Nuclear Energy,2015,85:380-385.
[22]B.Wu,Z.Chen,J.Song,et al.Advanced Geometry Navigation Methods without Cavity Representation for Fusion Reactors[R].MC SNA MC 2015,Nashville,April 19-23,2015.
[23]P.Long,Q.Zeng,T.He,et al.Development of a Geometry-Coupled Visual Analysis System for MCNP[J].Progress in Nuclear Science and Technology,2011,2:280-283.
[24]Z.Chen,J.Song,H.Zheng,et al.Optimal Spatial Subdivision Method for Improving Geometry Navigation Performance in Monte Carlo Particle Transport Simulation[J].Annals of Nuclear Energy,2015,76:479.
[25]Z.Chen,J.Song,G.Sun,et al.Geometry Navigation Acceleration based on Automatic Neighbour Search and Bounding Box in Monte Carlo Simulation[R].Proceeding of PHYSOR2014-The Role of Reactor Physics Toward a Sustainable Future,Nara,Japan 2014.
[26]Y.Wu,G.Song,R.Cao,et al.Development of Accurate/Advanced Radiotherapy Treatment Planning and Quality Assurance System(ARTS)[J].Chinese Physics C(HEP&NP),2008,32(Suppl.Ⅱ):177-182.
[27]Y.Yan,J.Song,H.Zheng,et al.On-the-fly Diagnostic Source Convergence Acceleration Methodology for Monte Carlo Criticality Calculation[R].Proceeding of 23th International Conference on Nuclear Engineering,May17-21,Chiba,Japan 2015.
[28]N.Horelik,B.Herman.Benchmark for Evaluation and Validation of Reactor Simulations[R].MIT,2013.
[29]N.Horelik,B.Herman,B.Forget,et al.MIT BEAVRS:Benchmark for Evaluation and Validation of Reactor Simulations[R].M&C 2013,May 5-9,Sun Valley,USA(2013).
[30]P.Wilson,R.Feder,U.Fischer,et al.State-of-theart 3-D Radiation Transport Methods for Fusion Energy Systems[J].Fusion Engineering and Design,2008,83:824-833.
[31]J.Song,G.Sun,Z.Chen,et al.Benchmarking of CAD-based SuperMC with ITER Benchmark Model[J].Fusion Engineering and Design,2014,89(11):2499-2503.
[32]Q.Zeng,L.Lu,A.Ding,et al.Update of ITER 3D Basic Neutronics Model with MCAM[J].Fusion Engineering and Design,2006,81(23-24):2773-2778.
[33]Q.Zeng,G.Wang,T.Dang,et al.Use of MCAM in Creating 3D Neutronics Model for ITER Buiiding[J].Fusion Engineering and Design,2012,87:1273-1276.
[34]D.Ying,Q.Zeng,Y.Qiu,et al.Assessment of Radiation Maps during Activated Divertor Moving in the ITER Building[J].Fusion Engineering and Design,2011,86(9-11):2087-2091.
[35]T Dang,D Ying,Q Yang,et al.First Neutronics Analysis for ITER Bio-shield Equatorial Port Plug[J].Fusion Engineering and Design.2012,87:1447-1452.
[36]Q.Yang,T.Dang,D.Ying,et al.Activation Analysis of Coolant Water in ITER Blanket and Divertor[J].Fusion Engineering and Design,2012,87(7-8),1310-1314.
[37]S.Yu,Q.Yang,C.Chen,etc.Shielding Design for Activated First Wall Transferring in ITER Hot Cell Building[J].Journal of Fusion Energy.2015,34(4):887-894.
[38]Q.Yang,B.Li,C.Chen,etc.Shielding Analysis for ITER Equatorial Port Cell During Blanket Replacement[J].Journal of Fusion Energy,2015,34(4):875-881.
[39]S.Zheng,E.Polunovskiy.Nuclear Heat of TF Inboard Legs with Fine Structures of Inboard Blanket[R].INAR-001,(2007).
[40]A.Turner,R.Pampin,M.Loughlin,et al.Nuclear Analysis and Shielding Optimisation in Support of the ITER In-Vessel Viewing System Design[J].Fusion Engineering and Design,2014,89:1949-1953.
[41]R.Pampina,S.Zheng,S.Lilley,et al.Activation Analyses Updating the ITER Radioactive Waste Assessment[J].Fusion Engineering and Design.2012,87:1230-1234.
[42]吴宜灿,柏云清,宋勇,等.中国铅基研究反应堆概念设计研究[J].核科学与工程,2014,34(2):56-63.
[43]Y.Wu,Y.Bai,Y.Song,et al.Development Strategy and Conceptual Design of China Lead-based Research Reactor[J].Annals of Nuclear Energy,2016,87:511-516.