紧凑 Tokamak(球形环)聚变堆第一壁及中心导体柱上中子负荷及核热计算与分析

CALCULATION AND ANALYSIS OF NEUTRON WALL LOAD AND NUCLEAR HEAT IN THE FIRST WALL AND CENTER CONDUCTOR POST OF A COMPACT TOKAMAK(SPHERICAL TORUS) FUSION REACTOR

采用通用蒙特卡罗粒子输运程序ＭＣＮＰ／３８计算低环径比Ｔｏｋａｍａｋ（紧凑环或球形环）聚变堆第一壁及中心导体上的中子壁负荷分布和核热沉积分布，并与常规Ｔｏｋａｍａｋ堆第一壁上中子壁负荷分布和核热沉积分布进行比较、分析。结果表明，在中子壁负荷归一化为１ＭＷ／ｍ２时，与常规Ｔｏｋａｍａｋ相比，在低环径比Ｔｏｋａｍａｋ堆第一壁及中心柱表面上中子壁负荷分布峰值并不比常规Ｔｏｋａｍａｋ堆第一壁上的峰值高，而且低于低环径比Ｔｏｋａｍａｋ堆整个第一壁上的平均值，而中心柱上的核热沉积峰值稍高于常规Ｔｏｋａｍａｋ堆第一壁上的核热沉积峰值，但对较高中子壁负荷情况，中心导体柱上的核热沉积和辐照损伤仍可能是比较严重和值得特别研究的问题。

Calculation of neutron wall load and nuclear heat in the first wall and the Center Conductor Post(CCP) of a Compact Tokamak-CT(or spherical torus) fusion reactor is carried out using the Monte Carlo code MCNP/3B. The results are compared with those of a reference Regular Tokamak(RT) fusion reactor and show that, on the basis of normalized neutron wall load( P w) of 1MW/m 2, the peak of P w on the CCP is not higher than that. P w of RT and also not higher than the average value of P w on the whole first wall of CT, and the maximum nuclear heat exists at midplane of CCP and is a little higher than that of first wall of RT, but the high nuclear heat and radiation damage in the CCP of the CT with a high neutron wall load may cause some problems to be further studied.