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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。
In inertial confinement fusion deuterium tritium cryogenic target preparation, the deuterium and tritium feedstock gas content is strictly limited. In order to control the content of a small amount of fuel, it is necessary to carry out related hydrogen isotope separation research and engineering development. According to the principle of Thermal Cycling Absorption Process (TCAP) and pre-cold experimental data, a set of small-scale experimental system for purification of heat was developed. The system is equipped with a 2 m long, 6.4 mm outer diameter palladium / diatomaceous earth packed column for filtration of 氕. According to the purification process design, 10% of the total adsorption capacity of the feed gas from the input end of the packed column, after a heating and cooling cycle output from the other end of the column, 累 accumulated in the column, and thus the purification of feed gas. Through the preliminary exploration of the purification process, after the continuous input of 33 times feed gas, the content of the column contents increased from 12% to 52%, the product gas content decreased from 12% to 3% and the deuterium-tritium fuel recovery rate was 82.5% Effective enrichment of column 氕, and effective filtration of 氕 in deuterium-tritium gas.