核融合炉燃料精製系を対象としたパラジウム拡散器の解析と設計

Abstract

Characteristics of tube-type palladium diffuser for a fusion reactor fuel cleanup system was analyzed with mathematical models. It was proved that a diffuser can recover most of tritium from plasma effluent gas. Calculations gave the profiles of concentration and flow rate of hydrogen in the diffuser. Hydrogen recovery ratio was described as a function of axial dispersion coefficient and feed gas flow rate.Based on the results, dimensions and operating conditions of the diffuser can be estimated. A diffuser for fuel cleanup system was designed under the conditions of Tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory.