Study on the mechanical properties and microstructure of Zr-2.5wt% Nb pressure tube material

被引:8
|
作者
Ahn, Dong-Hyun [1 ]
Lim, Sangyeob [1 ]
Lee, Gyeong-Geun [1 ]
Chun, Young-Bum [1 ]
机构
[1] Korea Atom Energy Res Inst, 989-111 Daedeok Daero, Daejeon 34057, South Korea
基金
新加坡国家研究基金会;
关键词
Zr-2.5 wt%Nb pressure tube; Stress/strain measurements; Fracture behavior; Microstructure; Anisotropy; Hydride; X-RAY-DIFFRACTION; DISLOCATION-STRUCTURE; ZR-2.5NB; DEFORMATION; ZIRCONIUM; EVOLUTION; IRRADIATION; ZIRCALOY-2; STRENGTH; BEHAVIOR;
D O I
10.1016/j.jnucmat.2019.06.013
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In order to study the mechanical properties and the anisotropy of a Zr-2.5 wt%Nb pressure tube material, tensile tests along the principal tube directions, which are axial, transverse and radial, were performed at room temperature using a pressure tube. The effect of tube length was evaluated, by using samples from the tube's back-end, middle, and front-end. Strong anisotropy among the principal directions was found, and increased strengths were obtained with increased distance from the front-end location. Microstructure analysis by X-ray diffraction, electron backscatter diffraction, and scanning electron microscopy indicated that increasing defect density along the tube was the main reason for the increasing strength. Although texture mainly determined the anisotropy of the tensile strengths, the ratio between the axial and radial strengths could be considerably altered by hydride plates. Depending on how the hydride plate was placed with regard to the deformation direction, the yield strength and strain hardening ability were reduced differently by the hydride. The deterioration effect of the hydrides did not show linear dependency on the hydrogen contents due to other microstructure variations. We had a brief discussion about which parameters might result in the non-linear change found in the deterioration along the tube. (C) 2019 Elsevier B.V. All rights reserved.
引用
收藏
页码:458 / 471
页数:14
相关论文
共 50 条
  • [1] A study of superplasticity in a Zr-2.5wt%Nb pressure tube alloy
    Singh, RN
    Kishore, R
    Sinha, TK
    Kashyap, BP
    [J]. SUPERPLASTICITY IN ADVANCED MATERIALS - ICSAM-97, 1997, 243-2 : 499 - 504
  • [2] Hydride blister formation in Zr-2.5wt%Nb pressure tube alloy
    Singh, RN
    Kishore, R
    Sinha, TK
    Kashyap, BP
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2002, 301 (2-3) : 153 - 164
  • [3] Flow behaviour of a modified Zr-2.5wt%Nb pressure tube alloy
    Singh, RN
    Mukherjee, S
    Kishore, R
    Kashyap, BP
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2005, 345 (2-3) : 146 - 161
  • [4] Neutron activation analysis for chlorine in Zr-2.5wt%Nb coolant tube material
    Verma, R
    Parthasarathy, R
    [J]. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY-LETTERS, 1996, 214 (05): : 391 - 397
  • [5] Microstructure evolution and tensile properties of Zr-2.5wt%Nb pressure tubes processed from billets with different microstructures
    Kapoor, K
    Muralidharan, K
    Saratchandran, N
    [J]. JOURNAL OF MATERIALS ENGINEERING AND PERFORMANCE, 1999, 8 (01) : 61 - 67
  • [6] Microstructure evolution and tensile properties of Zr-2.5wt%Nb pressure tubes processed from billets with different microstructures
    K. Kapoor
    N. Saratchandran
    K. Muralidharan
    [J]. Journal of Materials Engineering and Performance, 1999, 8 : 61 - 67
  • [7] Effect of neutron irradiation on microstructure and mechanical properties of Zr-2.5Nb pressure tube
    Kim, YS
    Ahn, SB
    Oh, DJ
    Kim, SS
    Cheong, YM
    [J]. PRICM 4: FORTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, VOLS I AND II, 2001, : 2775 - 2778
  • [9] The effect of chlorine-induced fissures on the tensile properties of Zr-2.5wt% Nb
    Yan, D
    Eadie, RL
    [J]. JOURNAL OF MATERIALS SCIENCE LETTERS, 2000, 19 (22) : 2051 - 2053
  • [10] Phase analysis of hydrogen contained Zr-2.5wt%Nb CANDU pressure tube using plasmon energy loss analysis
    Lim, Sang-Yeob
    Kim, SungSoo
    Park, Jucheol
    Lee, Gyeong-Geun
    Chang, Kunok
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2021, 552