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
收藏
页码：947 / 947
页数：1
相关论文
共 23 条
  • [1] Deformation behavior of recrystallized and stress-relieved Zircaloy-4 fuel cladding under biaxial stress conditions
    Mihara, Takeshi
    Udagawa, Yutaka
    Amaya, Masaki
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2018, 55 (02) : 151 - 159
  • [2] Fracture behavior of recrystallized and stress-relieved Zircaloy-4 cladding under biaxial stress conditions
    Mihara, Takeshi
    Udagawa, Yutaka
    Amaya, Masaki
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2019, 56 (08) : 724 - 730
  • [3] Erratum to: Deformation behavior of recrystallized and stress-relieved Zircaloy-4 fuel cladding under biaxial stress conditions (J. Nucl. Sci. Technol., (2017), 10.1080/00223131.2017.1383213)
    Journal of Nuclear Science and Technology, 2021, 58 (08):
  • [4] Low cycle fatigue properties and microscopic deformation structure of Zircaloy-4 in recrystallized and stress-relieved conditions
    Xiao, L
    Gu, HC
    JOURNAL OF NUCLEAR MATERIALS, 1999, 265 (1-2) : 213 - 217
  • [5] Deformation induced microstructure of stress relieved Zircaloy-4 cladding
    Nelson, Malachi
    Samuha, Shmuel
    Sheyfer, Dina
    Kamerman, David
    Yang, David
    Song, Kay
    Hofmann, Felix
    Tischler, Jon
    Hosemann, Peter
    MATERIALS & DESIGN, 2025, 250
  • [6] The effect of hydride morphology on the failure strain of stress-relieved Zircaloy-4 cladding with an outer surface pre-crack under biaxial stress states
    Li, Feng
    Mihara, Takeshi
    Udagawa, Yutaka
    Amaya, Masaki
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2019, 56 (05) : 432 - 439
  • [7] EFFECT OF GRAIN SHAPE AND TEXTURE ON EQUI-BIAXIAL CREEP OF STRESS RELIEVED AND RECRYSTALLIZED ZIRCALOY-4
    MURTY, KL
    TANIKELLA, BV
    EARTHMAN, JC
    ACTA METALLURGICA ET MATERIALIA, 1994, 42 (11): : 3653 - 3661
  • [8] Circumferential creep properties of stress-relieved Zircaloy-4 and Zr-Nb-Sn-Fe cladding tubes
    Lee, S. Y.
    Kim, K. T.
    Hong, S. I.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 392 (01) : 63 - 69
  • [9] Behavior of irradiated Zircaloy-4 fuel cladding under simulated LOCA conditions
    Ozawa, Masaaki
    Takahashi, Toshimichi
    Homma, Toshihiko
    Goto, Ken
    2000, American Society for Testing and Materials, Conshohocken, PA, USA
  • [10] A comparative study of corrosion mechanisms in recrystallized and stress-relieved Zircaloy-4 by 3D-FIB tomography and ACOM-TEM
    Lin, Weitong
    Cao, Jin
    Hu, Haixiang
    Lin, Shaofang
    Lv, Qingyang
    Ren, Qisen
    Hu, Jing
    CORROSION SCIENCE, 2024, 233
123