Deformation behavior of recrystallized and stress-relieved Zircaloy-4 fuel cladding under biaxial stress conditions (vol 55, pg 151, 2017)

被引：0

|

作者：

Mihara, T.

Udagawa, Y.

Amaya, M.

机构：

来源：

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 2021年 / 58卷 / 08期

关键词：

D O I：

10.1080/00223131.2017.1393281

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

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页码：947 / 947

页数：1

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[22] Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes:: Part III.: Mechanical behavior of hydride in stress-relieved annealed and recrystallized ZIRCALOYs at 20 °C and 300 °C
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METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2003, 34 (03): : 579 - 588
[23] Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes: Part III. Mechanical behavior of hydride in stress-relieved annealed and recrystallized ZIRCALOYs at 20 °C and 300 °C
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Metallurgical and Materials Transactions A, 2003, 34 : 579 - 588