Nuclear Techniques ›› 2015, Vol. 38 ›› Issue (5): 50603-050603.doi: 10.11889/j.0253-3219.2015.hjs.38.050603

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles    

Protium enrichment system fabrication and process exploration for D-T fuel quality control

WANG Weiwei CHEN Xiaohua XIA Lidong LI Hairong LONG Xinggui   

  1. (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, China)
  • Received:2015-01-10 Revised:2015-03-04 Online:2015-05-10 Published:2015-05-08

Abstract: 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.

Key words: Hydrogen isotope separation, TCAP, Protium enrichment, Pd/k