小球形托卡马克嬗变堆堆芯参数分析  

Reactor Core Design of Spherical Tokamak Transmutation of Nuclear Wastes

作　　者：邓柏权[1] 严建成[1] 冯开明[1] 

机构地区：[1]核工业西南物理研究院,成都610041

出　　处：《核科学与工程》2002年第1期79-84,共6页Nuclear Science and Engineering

基　　金：国家自然科学基金重点项目 198895 0 3和 198895 0 2

摘　　要：本文探讨作为聚变能中间应用的一种可行性 :利用低环径比球状托卡马克堆的高能聚变中子嬗变核电站的核废物。计算了堆芯等离子体物理参数、中心柱增益并进行参数学分析、几种可能的电流驱动方案比较和中心柱冷却方案设计及其计算。为了减轻偏滤器和第一壁材料的要求 ,我们有意选择较低堆芯物理参数 ,较低的中子壁负载运行。结果表明中心柱增益较低。建议从理论上探索研究由球状托卡马克等离子体顺磁性 ,建立一个无力球马克极向电流壳为中心区提供大部分或全部Bt,旨在建立无中心柱的低径比球状托卡马堆。如果可行 。One of the possible midway application of fusion energy to transmuting nuclear wastes produced from nuclear power plants by utilizing the energetic fusion neutrons based on spherical tokamak reactor has been discussed.The plasma parameters and centerpost gain are calculated and parametric studies are performed.Several possible options of current drive schemes are compared.The centerpost-cooling scheme is designed.To alleviate the requirements of divertor and first wall materials,we choose in purpose lower level operation of reactor plasma parameter and neutron wall loading.However,results show the centerpost gain is too low.A suggestion has been made that the new theory on plasma paramagnetism creating a force-free spheromak current shell at edge region producing the entire B t for the spherical tokamak core region should be studied.The chief merits of such a scheme are elimination of problems related to center post (joule heat,neutron damage etc.).A center-post-free spherical tokamak would be possible,then the performances of spherical tokamak reactor would be much improved.ducedfromnuc

关 键 词：堆芯参数 球状托卡马克堆 嬗变核废物 顺磁性外极向电流壳 物理参数 设计 中心柱 水冷却系统 

分 类 号：TL631.24[核科学技术—核技术及应用]