离子回旋加热是用以维持聚变堆实现长脉冲、高功率稳态运行重要的加热手段之一。中国聚变工程试验堆(China Fusion Engineering Test Reactor,CFETR)的离子回旋加热天线将经由一个上窗口引入,其天线发射前端将占据一个包层的位置。由于...离子回旋加热是用以维持聚变堆实现长脉冲、高功率稳态运行重要的加热手段之一。中国聚变工程试验堆(China Fusion Engineering Test Reactor,CFETR)的离子回旋加热天线将经由一个上窗口引入,其天线发射前端将占据一个包层的位置。由于天线直接面对等离子体,受高通量中子辐照,因此需要评估天线的辐照损伤;另外,天线内部存在大量空隙,造成中子泄漏,对后部真空室、线圈等部件造成辐照影响,因此需要评估其屏蔽性能,支撑屏蔽设计。基于22.5°扇段的水冷包层CFETR模型,用cosMCNP软件将CAD模型转为中子学模型,使用MCNP5粒子输运程序和FENDL-2.1数据库,通过全局减方差(Global Variance Reduction,GVR)“onthe-fly”减方差方法,开展离子回旋加热天线核分析。计算了天线主要部件辐照损伤和核响应,包括中子通量、平均原子离位(Displacement Per Atom,DPA)、气体产生率和核热密度等,为后续天线冷却系统的设计和寿命评估提供数据;获得引入天线后相应位置的真空室、窗口以及纵场线圈的中子辐照损伤,以评估屏蔽是否满足需求。此外,天线占据包层位置,将导致氚增殖比(Tritium Breeding Ratio,TBR)降低,由原始的1.151降至1.147,降低0.35%。展开更多
This paper presents the nuclear analysis performance of the Chinese Fusion Engineering Test Reactor(CFETR)divertor region using the MCNP-5 Monte Carlo N-particles code in a 3 D geometry model.We assessed the nuclear r...This paper presents the nuclear analysis performance of the Chinese Fusion Engineering Test Reactor(CFETR)divertor region using the MCNP-5 Monte Carlo N-particles code in a 3 D geometry model.We assessed the nuclear responses of the divertor region component systems and evaluated their shielding capability,which can support the development strategy of the physical and engineering design of the CFETR.Model specification based on the latest CAD model of the CFETR divertor has been integrated into the CFETR MCNP reference model with a major/minor radius R=7.2 m/a=2.2 m in the 22.5°model,and a fusion-power range of around 1-1.5 GW.The nuclear heating and radiation damage of the divertor system are enhanced compared to that of the ITER and the earlier CFETR design.The initial nuclear responses of the toroidal field coil and vacuum vessel systems showed that the shielding of the current divertor design is not sufficient and optimization work has been carried out.We also carried out calculations and analysis using a hypothetical operating scenario of over 14 years.An excellent improvement in the nuclear performance has been obtained by the improved additional shielding block in the divertor region when referring to the ITER design limit,which can support the design of the future update of the divertor region systems of the CFETR.展开更多
基金supported by the National Key Research and Development Program of China(Nos.2017YFE0300500,2017YFE0300503)。
文摘This paper presents the nuclear analysis performance of the Chinese Fusion Engineering Test Reactor(CFETR)divertor region using the MCNP-5 Monte Carlo N-particles code in a 3 D geometry model.We assessed the nuclear responses of the divertor region component systems and evaluated their shielding capability,which can support the development strategy of the physical and engineering design of the CFETR.Model specification based on the latest CAD model of the CFETR divertor has been integrated into the CFETR MCNP reference model with a major/minor radius R=7.2 m/a=2.2 m in the 22.5°model,and a fusion-power range of around 1-1.5 GW.The nuclear heating and radiation damage of the divertor system are enhanced compared to that of the ITER and the earlier CFETR design.The initial nuclear responses of the toroidal field coil and vacuum vessel systems showed that the shielding of the current divertor design is not sufficient and optimization work has been carried out.We also carried out calculations and analysis using a hypothetical operating scenario of over 14 years.An excellent improvement in the nuclear performance has been obtained by the improved additional shielding block in the divertor region when referring to the ITER design limit,which can support the design of the future update of the divertor region systems of the CFETR.
