OUT-OF-PILE TRITIUM EXTRACTION FROM LITHIUM SILICATE

被引：20

作者：

BREITUNG, W ^{[1
]}

ELBEL, H ^{[1
]}

LEBKUCHER, J ^{[1
]}

SCHUMACHER, G ^{[1
]}

WERLE, H ^{[1
]}

机构：

[1] KERNFORSCHUNGSZENTRUM KARLSRUHE GMBH,INST MAT & FESTKORPERFORSCH,D-7500 KARLSRUHE 1,FED REP GER

来源：

JOURNAL OF NUCLEAR MATERIALS | 1988年 / 155卷

关键词：

Ceramic Materials - Lithium Compounds--Radiation Effects - Neutrons - Nuclear Reactors; Breeder--Breeding Blankets - Tritium;

D O I：

10.1016/0022-3115(88)90299-1

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Tritium release from various neutron-irradiated samples of lithium meta- and orthosilicate has been studied in annealing experiments. Some of the samples have previously been tested in-pile. The temperature has been varied systematically and the influence of purge gas composition, flow rate and pressure and of moisture in the purge gas and samples has been tested. In agreement with previous results, release from orthosilicate was found to be faster than from metasilicate. The experimental release has been compared with theoretical predictions assuming various processes (diffusion, trapping, recombination). These comparisons and other evidence indicate that the tritium release in our out-of-pile tests, especially from the orthosilicate samples, is mainly determined by moisture in the samples and/or the purge gas.

引用

页码：507 / 512

页数：6