VERIFICATION OF A MODEL FOR IN-REACTOR CREEP TRANSIENTS IN ZIRCONIUM

被引：32

作者：

MACEWEN, SR ^{[1
]}

FIDLERIS, V ^{[1
]}

机构：

[1] ATOM ENERGY CANADA LTD, NUCL LABS, CHALK RIVER K0J 1J0, ONTARIO, CANADA

来源：

PHILOSOPHICAL MAGAZINE | 1975年 / 31卷 / 05期

关键词：

D O I：

10.1080/00318087508226834

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

引用

页码：1149 / 1157

页数：9

共 50 条

[21] IN-REACTOR CREEP OF COLD-WORKED ZIRCALOY-2 AND ZIRCONIUM-2.5 PERCENT NIOBIUM
ROSSROSS, PA
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1967, 10 (01): : 114 - &
[22] MORPHOLOGY OF OUT-REACTOR AND IN-REACTOR CORROSION SCALES ON ZIRCONIUM ALLOYS
MANOLESCU, AV
JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1987, 134 (8B) : C423 - C423
[23] Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys
Cox, B
JOURNAL OF NUCLEAR MATERIALS, 2005, 336 (2-3) : 331 - 368
[24] INVESTIGATION OF IN-REACTOR CREEP AND IRRADIATION GROWTH OF ZIRCONIUM-2.5 WT-PERCENT NIOBIUM CHANNEL TUBES
GONCHAROV, VV
PLATONOV, PA
IVANOV, AN
FROLOV, IA
JOURNAL OF NUCLEAR MATERIALS, 1980, 90 (1-3) : 224 - 231
[25] Relationship between in-reactor stress relaxation and irradiation creep
Foster, JP
Gilbert, ER
Bunde, K
Porter, DL
JOURNAL OF NUCLEAR MATERIALS, 1998, 252 (1-2) : 89 - 97
[26] FACILITY FOR IN-REACTOR CREEP TESTING OF FUEL CLADDING.
Kohn, E.
Wright, M.G.
1600,
[27] IN-REACTOR CREEP OF ZR-2.5 AT PERCENT NB
GILBERT, ER
JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) : 105 - &
[28] TEMPERATURE-DEPENDENCE OF THE IN-REACTOR CREEP OF COPPER AND ALUMINUM
AITKHOZHIN, ES
IBRAGIMOV, SS
CHUMAKOV, EV
SOVIET ATOMIC ENERGY, 1990, 69 (03): : 719 - 723
[29] Stress state dependence of in-reactor creep and swelling Part I: Continuum plasticity model
Hall, M. M., Jr.
JOURNAL OF NUCLEAR MATERIALS, 2010, 396 (01) : 112 - 118
[30] IN-REACTOR DEFORMATION OF ZIRCONIUM ALLOY TUBES AT 330-K
IBRAHIM, EF
JOURNAL OF NUCLEAR MATERIALS, 1981, 101 (1-2) : 1 - 8

← 1 2 3 4 5 →