RELEASE BEHAVIOR OF METALLIC FISSION-PRODUCTS FROM HTGR FUEL-PARTICLES AT 1600-DEGREES TO 1900-DEGREES-C

被引：64

作者：

MINATO, K ^{[1
]}

OGAWA, T ^{[1
]}

FUKUDA, K ^{[1
]}

SEKINO, H ^{[1
]}

MIYANISHI, H ^{[1
]}

KADO, S ^{[1
]}

TAKAHASHI, I ^{[1
]}

机构：

[1] JAPAN ATOM ENERGY RES INST,DEPT HOT LABS,TOKAI,IBARAKI 31911,JAPAN

来源：

JOURNAL OF NUCLEAR MATERIALS | 1993年 / 202卷 / 1-2期

关键词：

D O I：

10.1016/0022-3115(93)90027-V

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Release behavior of metallic fission products from the Triso-coated UO2 particles was studied by postirradiation heating tests in the temperature range 1600 to 1900-degrees-C (1873 to 2173 K) and subsequent postheating examinations. The fission gas release monitoring and the postheating examinations revealed that no pressure vessel failure occurred in the tests. Ceramographic observations showed no palladium attack and thermal decomposition of SiC. Cs-137, Cs-134, Ag-110m, Eu-154 and Eu-155 were released from the coated particles through the coating layers during postirradiation heating. The diffusion coefficient of Cs-137 in the SiC layer was evaluated from the release curves based on a simple diffusion model assuming a one-layer coated particle. Fractional release measurements suggested that the diffusion coefficient of Ag-110m in SiC be larger than that of Cs-137.

引用

页码：47 / 53

页数：7

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