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

页码：138 / 149

页数：12

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