EVIDENCES FOR ENHANCED DUCTILITY DURING IRRADIATION CREEP

被引：17

作者：

NICHOLS, FA

机构：

来源：

MATERIALS SCIENCE AND ENGINEERING | 1970年 / 6卷 / 03期

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D O I：

10.1016/0025-5416(70)90046-7

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

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页码：167 / &

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[1] UNIRRADIATED IN-PILE AND POST-IRRADIATION LOW STRAIN RATE TENSILE PROPERTIES OF ZIRCALOY-4
AZZARTO, FJ
BALDWIN, EE
WIESINGE.FW
LEWIS, DM
[J]. JOURNAL OF NUCLEAR MATERIALS, 1969, 30 (1-2) : 208 - &
[2] Buckley S. N., 1962, PROPERTIES REACTOR M, P413
[3] UNIAXIAL IN-REACTOR CREEP OF ZIRCONIUM ALLOYS
FIDLERIS, V
[J]. JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) : 51 - &
[4] IN-REACTOR CREEP OF ZR-2.5 AT PERCENT NB
GILBERT, ER
[J]. JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) : 105 - &
[5] A THEORY FOR FLOW OF POLYCRYSTALS
HART, EW
[J]. ACTA METALLURGICA, 1967, 15 (09): : 1545 - &
[6] THEORY OF TENSILE TEST
HART, EW
[J]. ACTA METALLURGICA, 1967, 15 (02): : 351 - &
[7] APPLICATION OF GENERALISED THEORY OF YIELDING CREEP TO IRRADIATION CREEP IN ZIRCONIUM ALLOYS
HESKETH, RV
[J]. JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) : 77 - &
[8] IRRADIATION CREEP IN GRAPHITE AT 40 DEGREES C
HESKETH, RV
[J]. PHILOSOPHICAL MAGAZINE, 1965, 11 (113): : 929 - &
[9] HESKETH RV, 1968, BNL50083C52, P389
[10] RADIATION-ENHANCED RELAXATION IN ZIRCALOY-4 AND ZR/2.5 WT PERCENT NB/0.5 WT PERCENT CU ALLOYS
KREYNS, PH
BURKART, MW
[J]. JOURNAL OF NUCLEAR MATERIALS, 1968, 26 (01) : 87 - &