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ST嬗变堆中心柱的中子学及中子辐照效应研究 被引量:2

STUDY OF NEUTRONICS AND NEUTRON IRRADIATION EFFECTS FOR SPHERICAL TOKAMAK CENTER-POST
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摘要 基于先进核数据库ENDF B VI和计算机程序对ST嬗变堆中心柱的中子学及辐照损伤的二维分析计算结果 ,分别对中心柱导体因中子辐照影响而引起电阻率、电阻、电流和欧姆电阻功率等的沿径向不均匀分布 ,以及辐照损伤对中心柱热工水力问题及更换寿命的影响进行了分析和计算。结果表明 ,中子辐照直接改变了中心柱导体材料的电阻率分布。热工 水力学分析和计算表明 ,电流不均匀分布可显著地延长中心柱的使用寿命 ,并估算出ST嬗变堆中心柱设计的更换寿命大约 Based on the advanced nuclear data library ENDF/B-VI and two-dimensional analysis and calculation of center-post neutronics and damage for ST-driven transmutation reactor by means of computer codes,the radial non-uniform distributions of resistivity,current density and ohmic resistive power density for center-post conductor,which are caused by neutron irradiation,as well as influence of neutron irradiation on thermo-hydraulics issue and changing lifetime for a center-post have been analyzed and calculated.It concludes that neutron irradiation directly changes the distribution of resistivity of the center-post conductor material.It also concludes from thermo-hydraulic analysis and calculation that non-uniform distribution of current density can prolong the lifetime of a center-post.Finally,it is estimated that the changing time of center-post for a spherical tokamak transmutation reactor is about 8 years.
出处 《核聚变与等离子体物理》 CAS CSCD 北大核心 2002年第1期25-30,共6页 Nuclear Fusion and Plasma Physics
基金 国家自然科学基金资助项目 (196 85 0 0 8)
关键词 球形托卡马克 中心柱 中子学 辐照损伤 ST嬗变堆 中子辐照效应 Spherical tokamak Center-post Neutronics Irradiation effect
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  • 1Cheng E T,USDOE Phase Ir eport TSIR 45,1996年
  • 2Wong C P C,ANS 9th Topical Meeting on the Technology of Fusion Energy,1990年

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