CFETR集成设计平台的核热耦合模块开发
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摘要
正在研发的中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)集成设计平台包括物理设计平台和工程设计平台,工程设计平台采用模块化方式,包括磁体、真空室、偏滤器、中子学等模块。模块设计中涉及用计算流体动力学(Computational Fluid Dynamics,CFD)软件来对堆内部件开展热工水力分析,CFD的热源项包括中子学计算产生的核热,而中子学分析软件(如Monte Carlo N particle transport code,MCNP)核热输出结果文件存在CFD软件无法直接读取等问题。因此,基于网格-网格插值和点-点插值法,开发了中子学与CFD核热耦合模块,提供两种途径实现高精度的三维核热耦合。使用CFX软件,以CFETR的一种氦冷陶瓷包层(Helium Cooled Ceramic Breeder blanket,HCCB)中增殖单元模块为对象,进行了热工水力分析,计算结果表明了核热耦合模块功能的可靠性。
[Background] The China fusion engineering test reactor(CFETR) under development,mainly consists of a physical design platform and an engineering design platform,and the latter includes various modules.In the design of the modules,computational fluid dynamics(CFD) software is used for thermal-hydraulic analysis of the fusion in-vessel components of which the nuclear heating is a necessary source term generated from neutronics calculations of Monte Carlo N particle transport code(MCNP).[Purpose] This study aims to transfer the 3D nuclear heating profiles from MCNP to CFD software and develop neutronics-thermal hydraulics coupling module for CFETR integration design platform.[Methods] The 3D nuclear heating profiles were processed by two different interpolation methods:element-to-element mapping method and point-to-point mapping method,and the 1D nuclear heating profiles were also processed for comparison.Thermal-hydraulic analysis based on breeder unit of the helium cooled ceramic breeder blanket(HCCB) for CFETR was performed on ANSYS CFX for verification.The total interpolated nuclear heating,heating distributions and temperature distributions were compared in detail according to the CFX simulation results.[Results] Comparison results showed that all schemes satisfied the conservation of nuclear heating with appropriate mesh.Element-to-element mapping method and point-to-point mapping method differs in the heating peak value due to the different interpolation method.[Conclusion] The neutronics-thermal hydraulics coupling module proposed in this paper possesses high reliability for CFETR integration design platform.
[Background] The China fusion engineering test reactor(CFETR) under development,mainly consists of a physical design platform and an engineering design platform,and the latter includes various modules.In the design of the modules,computational fluid dynamics(CFD) software is used for thermal-hydraulic analysis of the fusion in-vessel components of which the nuclear heating is a necessary source term generated from neutronics calculations of Monte Carlo N particle transport code(MCNP).[Purpose] This study aims to transfer the 3D nuclear heating profiles from MCNP to CFD software and develop neutronics-thermal hydraulics coupling module for CFETR integration design platform.[Methods] The 3D nuclear heating profiles were processed by two different interpolation methods:element-to-element mapping method and point-to-point mapping method,and the 1D nuclear heating profiles were also processed for comparison.Thermal-hydraulic analysis based on breeder unit of the helium cooled ceramic breeder blanket(HCCB) for CFETR was performed on ANSYS CFX for verification.The total interpolated nuclear heating,heating distributions and temperature distributions were compared in detail according to the CFX simulation results.[Results] Comparison results showed that all schemes satisfied the conservation of nuclear heating with appropriate mesh.Element-to-element mapping method and point-to-point mapping method differs in the heating peak value due to the different interpolation method.[Conclusion] The neutronics-thermal hydraulics coupling module proposed in this paper possesses high reliability for CFETR integration design platform.
引文
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8 Chen X M,Ma X B,Jiang K C,et al.Thermal hydraulic design and analysis of a water-cooled ceramic breeder blanket with superheated steam for CFETR[J].Plasma Science and Technology,2015,17(9):787 791.DOI:10 .1088/1009-0630/17/9/11.
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11 陈军,曹良志,郑友琦,等.基于蒙特卡罗方法和CFD方法的物理-热工耦合计算[J].原子能科学技术,2016,50(2):301 305.DOI:10.7538/yzk.2016.50.02.0301.CHEN Jun,CAO Liangzhi,ZHENG Youqi,et al.Neutronics and thermal-hydraulics coupling calculation based on Monte Carlo and CFD method[J].Atomic Energy Science and Technology,2016,50(2):301 305.DOI:10.7538/yzk.2016.50.02.0301.
12 Ying A,Narula M,Abdou M,et al.Toward an integrated simulation predictive capability for fusion plasma chamber systems[J].Fusion Science and Technology,2009,56(2):918 924.DOI:10.13182/FST09-A9027.
13 Wilson P,Tautges T,Kraftcheck J,et al.Acceleration techniques for the direct use of CAD-based geometry in fusion neutronics analysis[J].Fusion Engineering and Design,2010,85(10):1759 1765.DOI:10.1016/j.fusengdes.2010.05.030.
14 Qiu Y F,Lu P,Ulrich F,et al.A generic data translation scheme for the coupling of high-fidelity fusion neutronics and CFD calculations[J].Fusion Engineering and Design,2014,89(7):1330 1335.DOI:10.1016/j.fusengdes.2014.02.044.
15 Legensky S,Edwards D,Bush R,et al.CFD general notation system(CGNS)-status and future directions[C].40 th AIAA Aerospace Sciences Meeting&Exhibit,2002:752.
16 陶文铨.数值传热学[M].西安:西安交通大学出版社,2001.TAO Wenquan.Numerical heat transfer[M].Xi'an:Xi'an Jiaotong University Press,2001.
17 何泽鸿,叶民友,王忠伟,等.MCNP与后处理软件耦合应用程序开发[J].核技术,2015,38(6):060601.DOI:10 .11889/j.0253-3219.2015.hjs.38.060601.HE Zehong,YE Minyou,WANG Zhongwei,et al.MCNP coupled with post-processing software application development[J].Nuclear Techniques,2015,38(6):060601.DOI:10.11889/j.0253-3219.2015.hjs.38.060601.
2 Ye M Y,Wang S J,Wang Z W,et al.Development of system code of CFETR design[C].Proceedings of 26th Symposium on Fusion Engineering(SOFE),Austin,TX,USA,2015.
3 Wang S J,Ye M Y,Zhu C,et al.The Integration platform development of system code for CFETR[J].IEEE Transactions on Plasma Science,2016,44(9):1745 1750.DOI:10.1109/TPS.2016.2598599.
4 Zhang J W,Ye M Y,Peng X B,et al.Preliminary design and verification of divertor module of CFETR system code[J].IEEE Transactions on Plasma Science,2016,44 (9):1763 1767.DOI:10.1109/TPS.2016.2599264.
5 Zhu C,Ye M Y,Liu X F,et al.Development of vacuum vessel design and analysis module for CFETR integration design platform[J].Science and Technology of Nuclear Installations,2016:5321057.DOI:10.1155/2016/5321057.
6 Zhou G M,Li M,Liu Q W,et al.Thermal analysis of breeder unit for helium cooled solid breeder blanket of Chinese fusion engineering test reactor[J].Journal of Fusion Energy,2015,34(2):339 345.DOI:10.1007/s10894-014-9798-y.
7 Zanino R,Richard L S,Subba F,et al.CFD analysis of a regular sector of the ITER vacuum vessel Part II:Thermal-hydraulic effects of the nuclear heat load[J].Fusion Engineering and Design,2013,88(12):3248 3262.DOI:10.1016/j.fusengdes.2013.10.005
8 Chen X M,Ma X B,Jiang K C,et al.Thermal hydraulic design and analysis of a water-cooled ceramic breeder blanket with superheated steam for CFETR[J].Plasma Science and Technology,2015,17(9):787 791.DOI:10 .1088/1009-0630/17/9/11.
9 Thomas J W,Zhong Z,Sofu T,et al.Methodology for coupling computational fluid dynamics and integral transport neutronics[C].Proceedings of PHYSOR 2004-The Physics of Fuel Cycles and Advanced Nuclear Systems:Global Developments,Chicago,IL,USA,2004.
10 何杰,夏晓彬,蔡军,等.2 MW液态钍基熔盐实验堆主屏蔽温度场分析[J].核技术,2016,39(4):040601.DOI:10.11889/j.0253-3219.2016.hjs.39.040601.HE Jie,XIA Xiaobin,CAI Jun,et al.Temperature field analysis for the main shielding of the 2-MW thorium-based molten salt experimental reactor[J].Nuclear Techniques,2016,39(4):040601.DOI:10 .11889/j.0253-3219.2016.hjs.39.040601.
11 陈军,曹良志,郑友琦,等.基于蒙特卡罗方法和CFD方法的物理-热工耦合计算[J].原子能科学技术,2016,50(2):301 305.DOI:10.7538/yzk.2016.50.02.0301.CHEN Jun,CAO Liangzhi,ZHENG Youqi,et al.Neutronics and thermal-hydraulics coupling calculation based on Monte Carlo and CFD method[J].Atomic Energy Science and Technology,2016,50(2):301 305.DOI:10.7538/yzk.2016.50.02.0301.
12 Ying A,Narula M,Abdou M,et al.Toward an integrated simulation predictive capability for fusion plasma chamber systems[J].Fusion Science and Technology,2009,56(2):918 924.DOI:10.13182/FST09-A9027.
13 Wilson P,Tautges T,Kraftcheck J,et al.Acceleration techniques for the direct use of CAD-based geometry in fusion neutronics analysis[J].Fusion Engineering and Design,2010,85(10):1759 1765.DOI:10.1016/j.fusengdes.2010.05.030.
14 Qiu Y F,Lu P,Ulrich F,et al.A generic data translation scheme for the coupling of high-fidelity fusion neutronics and CFD calculations[J].Fusion Engineering and Design,2014,89(7):1330 1335.DOI:10.1016/j.fusengdes.2014.02.044.
15 Legensky S,Edwards D,Bush R,et al.CFD general notation system(CGNS)-status and future directions[C].40 th AIAA Aerospace Sciences Meeting&Exhibit,2002:752.
16 陶文铨.数值传热学[M].西安:西安交通大学出版社,2001.TAO Wenquan.Numerical heat transfer[M].Xi'an:Xi'an Jiaotong University Press,2001.
17 何泽鸿,叶民友,王忠伟,等.MCNP与后处理软件耦合应用程序开发[J].核技术,2015,38(6):060601.DOI:10 .11889/j.0253-3219.2015.hjs.38.060601.HE Zehong,YE Minyou,WANG Zhongwei,et al.MCNP coupled with post-processing software application development[J].Nuclear Techniques,2015,38(6):060601.DOI:10.11889/j.0253-3219.2015.hjs.38.060601.