FEB聚变实验增殖堆氚投料量及氚回收的研究  

STUDIES OF TRITIUM INVENTORY AND TRITIUM RECOVERYFOR THE FEB FUSION EXPERIMENTAL BREEDER

作　　者：邓柏权[1] 张国书[1] 王岷[1] 邓培智[1] 黄锦华[1] 

机构地区：[1]核工业西南物理研究院

出　　处：《核聚变与等离子体物理》1998年第2期18-24,共7页Nuclear Fusion and Plasma Physics

基　　金：国家863高技术

摘　　要：运用三维ＭｏｎｔｅＣａｒｌｏ程序ＭＯＲＳＥ－ＣＧＴ，计算了聚变实验增殖堆ＦＥＢ满功率运行１０ｄ后外侧包层各区中的氚浓度、运行１ｄ后内侧包层各区中的氚浓度及运行１ＦＰＹ（满功率年）后Ｂｅ球中的氚投料量，设计了ＦＥＢ堆现场氚的分布流程图。采用组合的燃料净化系统和低温分馏法从等离子体排出气体中回收氚，讨论了从液态锂中回收氚的几种方案用于ＦＥＢ的可行性。おhe tritium concentrations in liquid lithium of each tritium breeding zone of the FEB have been calculated after 10 days full power operation for outboard blanket and one day operation for inboard blanket using tritium breeding ratios calculated with the threedimensional Monte Carlo code MORSECGT. The tritium inventory in the Be pellets is also estimated after one full power year operation. The tritium flow sheet for the FEB reactor site is preliminarily outlined. Tritium recovery from plasma exhaust gas has been considered by combining fuel clearup unit with cryogenic distillation. Four possible approaches to retrieve tritium from liquid lithium may be applied to the FEB.

关 键 词：氚投料量 氚回收 聚变实验增殖堆 FEB增殖包层 

分 类 号：TL64[核科学技术—核技术及应用]