cosRMC复杂曲面开发及在聚变中子学的应用

Development of Complex Surface in cosRMC and Application in Fusion Neutronics

  • 摘要: 中国聚变工程实验堆(CFETR)是我国自主设计和研制的重大科学工程,CFETR旨在与ITER相衔接和补充,为研制DEMO级别聚变堆电站提供必要的技术。蒙特卡罗方法在聚变中子学与屏蔽设计等方面具有重要作用。本文基于自主化蒙特卡罗程序cosRMC,研究了蒙特卡罗复杂曲面建模的数学模型和计算方法,开发了复杂曲面建模功能,并通过PPCS(power plant conceptual study)模型验证了该功能实现的正确性。然后构建了CFETR的三维精细化模型,并利用该模型对CFETR包层设计中的关键中子学参数进行计算分析。结果表明,cosRMC对中子学参数氚增殖比、中子壁载荷和核热沉积的计算结果与MCNP的计算值吻合良好,相对偏差均小于5%,满足工程设计需求。研究证明了cosRMC应用于聚变堆包层中子学分析的正确性和有效性。CFETR中子学参数的计算分析,也为其设计和优化提供了参考。

     

    Abstract: China Fusion Engineering Experimental Reactor (CFETR) is an important scientific project designed and developed independently in China. CFETR aims to connect and supplement with ITER and provide necessary technology for the development of DEMO grade fusion reactor power station. Monte Carlo method plays an important role in the fusion neutronics and shielding design of fusion reactor. In this paper, the mathematic model and computing method of complex surface modeling of Monte Carlo code were studied and the function was developed in the selfdeveloped Monte Carlo code cosRMC. The correctness of this function was verified by PPCS (power plant conceptual study) model. Then a threedimensional refined model of CFETR was constructed and used to calculate and analyze the key neutronics parameters in the design of CFETR blanket. The results show that the tritium breeding ratio, neutron wall loading and the nuclear heat deposition are in good agreement with those calculated by MCNP, and the relative discrepancies are all within 5%, which meets the requirements of engineering design. The applications of cosRMC for neutronics analysis of fusion reactor cladding are proved to be correct and effective. The analysis of neutronics parameter of CFETR also provides the reference for its designs and optimizations.

     

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