MODEL FOR IN-REACTOR DENSIFICATION OF UO2

被引：21

作者：

MACEWEN, SR ^{[1
]}

HASTINGS, IJ ^{[1
]}

机构：

[1] ATOM ENERGY CANADA LTD, NUCL LABS, CHALK RIVER, ONTARIO, CANADA

来源：

PHILOSOPHICAL MAGAZINE | 1975年 / 31卷 / 01期

关键词：

D O I：

10.1080/14786437508229291

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

引用

页码：135 / 143

页数：9

共 30 条

[1] OXYGEN AND URANIUM DIFFUSION IN URANIUM DIOXIDE (A REVIEW) [J].

BELLE, J .

JOURNAL OF NUCLEAR MATERIALS, 1969, 30 (1-2) :3-&

[2] RATE THEORY OF SWELLING DUE TO VOID GROWTH IN IRRADIATED METALS [J].

BRAILSFORD, AD ;

BULLOUGH, R .

JOURNAL OF NUCLEAR MATERIALS, 1972, 44 (02) :121-+

[3] GROWTH AND STABILITY OF VOIDS IN IRRADIATED METALS [J].

BULLOUGH, R ;

EYRE, BL ;

PERRIN, RC .

NUCLEAR APPLICATIONS AND TECHNOLOGY, 1970, 9 (03) :346-+

[4] SINTERING OF GRAIN-BOUNDARY CAVITIES IN URANIUM-DIOXIDE [J].

BURTON, B ;

REYNOLDS, GL .

JOURNAL OF NUCLEAR MATERIALS, 1972, 45 (01) :10-14

[5] DENSIFICATION IN MIXED-OXIDE FUEL DURING FAST-REACTOR IRRADIATION [J].

CARLSON, MCJ .

NUCLEAR TECHNOLOGY, 1974, 22 (03) :335-359

[6]

CHERNOCK WP, 1974, APR AM POW C CHIC

[7]

COLLINS DA, 1973, BRIT NUCLEAR ENERGY

[8]

DOLLINS CC, 1971, RADIAT EFF, V11, P33

[9]

HARKNESS SD, 1971, METALL TRANS, V2, P1457

[10]

HASTINGS IJ, UNPUBLISHED RESULTS

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