Tensile properties and fracture toughness of Zr-2.5Nb alloy pressure tubes of IPHWR220

被引：13
|
作者：
Khandelwala, H. K. [1 ,2 ]
Singh, R. N. [1 ,2 ]
Bind, A. K. [1 ]
Sunil, S. [1 ]
Chakravartty, J. K. [1 ]
Ghosh, A. [3 ]
Dhandharia, P. [3 ]
Bhachawat, D. [3 ]
Shekhar, R. [4 ]
Kumar, Sunil Jai [4 ]
机构：
[1] Bhabha Atom Res Ctr, Mech Met Div, Bombay 400085, Maharashtra, India
[2] Homi Bhabha Natl Inst, Bombay 400094, Maharashtra, India
[3] Nucl Power Corp India Ltd, NUB, Engn Directorate, Bombay 400094, Maharashtra, India
[4] Bhabha Atom Res Ctr, Natl Ctr Composit Characterisat Mat, Hyderabad 500062, Andhra Pradesh, India
来源：
NUCLEAR ENGINEERING AND DESIGN | 2015年 / 293卷
关键词：
ZIRCONIUM ALLOYS; HYDROGEN CONTENT; TEMPERATURE; FABRICATION; CRACKING;
D O I：
10.1016/j.nucengdes.2015.07.048
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：
The pressure tubes of Indian Pressurized Heavy Water Reactor (IPHWR) of 220 MWe are made of Zr-2.5Nb alloy manufactured either from Double Melted (DM) or from Quadruple Melted (QM) ingots. These pressure tubes are manufactured by hot extrusion, two stages of cold pilgering with intermediate annealing and autoclaving. To achieve good in-reactor performance, it is required to have minimum variability in the mechanical properties of the pressure tube across its length and between tube to tube. In this work, tensile properties and fracture toughness parameters (J(max), dJ/da and CCL determined as per ASTM E1820-11 standard) of unirradiated Zr-2.5Nb alloy pressure tubes manufactured from DM and QM ingots using samples obtained from front and back end of the tubes is presented. The mechanical properties were evaluated in temperature range of 25-450 degrees C and compared with the corresponding data reported in literature for CANDU pressure tubes. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码：138 / 149
页数：12
相关论文
共 50 条
  • [1] Study of the impact of hydrides on the fracture toughness of Zr-2.5Nb alloy
    Janulionis, Remigijus
    Dundulis, Gintautas
    NUCLEAR ENGINEERING AND DESIGN, 2024, 416
  • [2] Influence of hydrogen content on fracture toughness of CWSR Zr-2.5Nb pressure tube alloy
    Singh, R. N.
    Bind, A. K.
    Srinivasan, N. S.
    Stahle, P.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 432 (1-3) : 87 - 93
  • [3] Effect of Thermal Cycling on Tensile Properties and Impact Toughness of Hydrided Zr-2.5Nb PT Material
    Murty, T. N.
    Kumar, Sushil
    Bind, A. K.
    Roy, B. N.
    Sahu, R. K.
    Mishra, J. K.
    Singh, R. N.
    TRANSACTIONS OF THE INDIAN INSTITUTE OF METALS, 2022, 75 (04) : 871 - 877
  • [4] Effect of hydrogen isotopes on tensile and fracture properties of Zr-2.5Nb pressure tube material
    Bind, A. K.
    Singh, R. N.
    INTERNATIONAL JOURNAL OF FRACTURE, 2021, 227 (02) : 193 - 204
  • [5] Overload fracture of flaw tip hydrides in Zr-2.5Nb pressure tubes
    Shek, Gordon K.
    Cui, Jun
    Perovic, Vuko
    Zirconium in the Nuclear Industry: 14th International Symposium, 2005, 1467 : 729 - 758
  • [6] Delayed hydride cracking behavior of Zr-2.5Nb alloy pressure tubes for PHWR700
    Sunil, S.
    Bind, A. K.
    Khandelwal, H. K.
    Singh, R. N.
    Chakravartty, J. K.
    JOURNAL OF NUCLEAR MATERIALS, 2015, 466 : 208 - 219
  • [7] Influence of hydrogen content on impact toughness of Zr-2.5Nb pressure tube alloy
    Singh, R. N.
    Viswanathan, U. K.
    Kumar, Sunil
    Satheesh, P. M.
    Anantharaman, S.
    Chakravartty, J. K.
    Stahle, P.
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (07) : 2425 - 2436
  • [8] Effect of radial hydride on room temperature fracture toughness of Zr-2.5Nb pressure tube material
    Gopalan, Avinash
    Bind, A. K.
    Sunil, Saurav
    Murty, T. N.
    Sharma, R. K.
    Samanta, Akanksha
    Soren, Amit
    Singh, R. N.
    JOURNAL OF NUCLEAR MATERIALS, 2021, 544
  • [9] Effect of direction of approach of test temperature on fracture toughness of Zr-2.5Nb pressure tube material
    Singh, R. N.
    Bind, A. K.
    Khandelwal, H. K.
    Rath, B. N.
    Sunil, S.
    Stahle, P.
    Chakravartty, J. K.
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2015, 621 : 190 - 197
  • [10] The development of Zr-2.5Nb pressure tubes for CANDU reactors
    Cheadle B.A.
    Journal of ASTM International, 2010, 7 (08):
12345