In-reactor creep behaviour of Zircaloy-2 under variable loading conditions

被引：0

作者：

McGrath, MA ^{[1
]}

机构：

[1] Inst Energiteknikk, OECD Halden Reactor Project, N-2007 Kjeller, Norway

来源：

ANNUAL MEETING ON NUCLEAR TECHNOLOGY '98, PROCEEDINGS | 1998年

关键词：

D O I：

暂无

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：

引用

页码：731 / 735

页数：5

共 50 条

[1] In-reactor creep behaviour of Zircaloy-2 under variable loading conditions
McGrath, MA
ANNUAL MEETING ON NUCLEAR TECHNOLOGY '98, PROCEEDINGS, 1998, : 731 - 735
[2] IN-REACTOR TUBULAR CREEP OF ZIRCALOY-2 AT 260 TO 300 DEGREES C
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JOURNAL OF NUCLEAR MATERIALS, 1973, 46 (02) : 169 - 182
[3] UNIAXIAL IN-REACTOR CREEP OF ZIRCALOY-2 - STRESS, FLUX, AND TEMPERATURE-DEPENDENCE
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[4] INFLUENCE OF MANUFACTURING PROCESS ON THE IN-REACTOR CREEP ANISOTROPY OF STRESS-RELIEVED ZIRCALOY-2 CLADDING
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VANSWAM, LF
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[5] IN-REACTOR CREEP OF COLD-WORKED ZIRCALOY-2 AND ZIRCONIUM-2.5 PERCENT NIOBIUM
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[7] Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure
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[8] Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure
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[9] Understanding the Drivers of In-Reactor Growth of β-Quenched Zircaloy-2 BWR Channels
Romero, Javier
Dahlback, Mats
Hallstadius, Lars
Ivermark, Maria
Ledergerber, Guido
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[10] HYDROGEN EMBRITTLEMENT OF ZIRCALOY-2 SHEET UNDER MULTIAXIAL LOADING CONDITIONS
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KOSS, DA
JOURNAL OF METALS, 1982, 34 (08): : 70 - 70

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