摘要
在惯性约束聚变氘氚冷冻靶制备中,对氘氚原料气中氕含量有严格限制。为控制少量燃料中氕含量,有必要开展相关氢同位素分离研究及工程研制。根据热循环吸附(Thermal Cycling Absorption Process,TCAP)原理及前期冷实验数据,研制了一套小型纯化热实验系统。系统内配置了一根长2 m、外径6.4 mm的钯/硅藻土填充柱用于对氕的过滤。按照纯化工艺设计,占总吸附量10%的原料气从填充柱一端输入,经过一次加热冷却循环后从柱另一端输出,氕在色谱柱内累积,进而实现原料气的纯化。经过纯化工艺初步探索,连续输入33次原料气后,柱内氕含量由12%累积到了52%,产品气中氕含量由12%降至3%,氘氚燃料回收率为82.5%,实现了柱内氕的有效富集,以及氘氚气体中氕的有效过滤。
Background： Due to an inverse factor to D-T fusion reaction, protium （H） content in D-T fuels is restricted for fuel quality control during Inertial Confinement Fusion （ICF） D-T cryogenic target fabrication. Purpose： This study aims to separate protium from a deuterium-tritium mixture in order to control protium content in DT fuels which is an important issue to support ICF related research work. Methods： A 2-m Palladium/kiesulghur （Pd/k） packed column with outer diameter of 6.4 mm is applied to filter protium, and a micro Thermal Cycling Absorption Process （TCAP） separation system is designed for protium enrichment in the column. When the feed gas （10% of total absorption amount） was input from the top end, the protium was accumulated and enriched in the column, resulting in the product gas from the bottom end purified after one heating-cooling cycle which is powered by a temperature control system-huber Unistat 912w. Results： After 33 automatic enrichment cycles in one testing batch, protium concentration in the column rised from 12% to 52% whilst the protium content in the product gas reduced to 3% compared with 12% protium content in the feed gas. The recycle rate of D-T by this batch was 82.5%. Conclusion： Protirm gets effective enriched in Pd/k filled column, and D-T mixture purification is effective by this enrichment system.
出处
《核技术》
CAS
CSCD
北大核心
2015年第5期92-96,共5页
Nuclear Techniques
基金
中国工程物理研究院冷冻靶充气冷冻课题基金资助
