INPILE TRITIUM RELEASE FROM CERAMIC BREEDER MATERIALS IN TRIDEX EXPERIMENTS 1-6

被引：5

作者：

KRUG, W ^{[1
]}

BAYS, HG ^{[1
]}

JUNEMANN, H ^{[1
]}

KRAUTHAUSEN, W ^{[1
]}

SCHMIDT, F ^{[1
]}

SEFERIADIS, J ^{[1
]}

WEISE, L ^{[1
]}

WERLE, H ^{[1
]}

机构：

[1] KERNFORSCHUNGSZENTRUM KARLSRUHE GMBH,W-7500 KARLSRUHE 1,GERMANY

来源：

FUSION ENGINEERING AND DESIGN | 1991年 / 17卷

关键词：

D O I：

10.1016/0920-3796(91)90038-R

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Dependence of tritium release on purge gas chemistry has been studied in the temperature range 350-600-degrees-C for a variety of lithium orthosilicate and metazirconate samples (mainly 0.5 mm diameter pebbles) in the TRIDEX series of purged inpile tests. TRIDEX results were found to be in reasonable agreement with previous inpile experiments. Tritium release is remarkably improved by adding small percentages of hydrogen to the helium purge gas and/or by reducing the oxygen partial pressure of the helium purge gas. Similar tritium release behaviour of different charges of spheres prepared from molten orthosilicate demonstrates reproducibility of this fabrication route.

引用

页码：65 / 71

页数：7

共 6 条

[1]

BREITUNG W, 1989, IN PRESS J NUCL MATE

[2]

DONNE MD, 1990, IN PRESS 16TH P S FU

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ROTH, E ;

VOLLATH, D .

JOURNAL OF NUCLEAR MATERIALS, 1988, 155 :544-548

[4]

KWAST H, 1990, IN PRESS 16TH P S FU

[5]

TANAKA S, 1989, IN PRESS J NUCL MATE

[6] THE LISA-2 EXPERIMENT - INSITU TRITIUM RELEASE FROM LITHIUM ORTHOSILICATE (LI4SIO4) [J].

WERLE, H ;

BREITUNG, W ;

BRIEC, M ;

CLEMMER, RG ;

ELBEL, H ;

HAFNER, HE ;

MASSON, M ;

SCHUMACHER, G ;

WEDEMEYER, H .

JOURNAL OF NUCLEAR MATERIALS, 1988, 155 :538-543

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