Estimation of neutron duct streaming with the feeder for the power supply system in the JT-60 tokamak fusion device facility

A. Sukegawa, Koichi Okuno
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Abstract

The estimation of neutron duct streaming with a feeder for the power supply system in a JT-60 Tokamak fusion device facility has been performed via neutoronics analysis using a simplified formula for the cylindrical duct streaming model and a suitable model based on the Monte Carlo technique. However, the safety margin is too large for the evaluation using a simplified formula in order to evaluate the neutron streaming of a duct with three feeders (each feeder of size 0.126 m × 0.357 m × 2 m) inside a cylindrical duct (0.8 m diameter × 2 m length in size). Further, a detailed evaluation of neutron streaming of a cylindrical duct with three feeders has not been performed in the facility. In this study, three-dimensional (3D) neutronics analysis using a real-model of the complex structured duct was performed to assess the safety margin of the simplified formula. It was confirmed that the neutron dose attenuation of the penetrating section in the duct using the simplified formula is approximately one order of magnitude larger than the real-model using the 3D calculation code.
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JT-60托卡马克聚变装置供电系统馈线中子管道流的估计
利用简化的圆柱形管道流模型公式和基于蒙特卡罗技术的合适模型,通过中子电子学分析对JT-60托卡马克聚变装置供电系统的中子管道流进行了估计。但是,在直径为0.8 m ×长度为2m的圆柱形风管中,采用简化公式评价具有3个给料器(每个给料器尺寸为0.126 m × 0.357 m × 2 m)的风管的中子流时,安全余量太大。此外,该设施还没有对带有三个进料器的圆柱形管道的中子流进行详细评估。在本研究中,使用复杂结构管道的实际模型进行了三维(3D)中子分析,以评估简化公式的安全裕度。用简化公式计算的导管穿透截面的中子剂量衰减比用三维计算程序计算的实际模型约大一个数量级。
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