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Journal ArticleDOI

Delayed hydride cracking in Zr–2.5Nb pressure tube material☆

TLDR
In this paper, the authors measured the DHC velocity along the axial direction of the double melted, cold worked and stress-relieved Zirconium-2.5Niobium pressure tube material in the temperature range of 162-283 °C.
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This article is published in Journal of Nuclear Materials.The article was published on 2002-08-01. It has received 58 citations till now.

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Journal ArticleDOI

Delayed hydride cracking of Zr-2.5%Nb pressure tube material due to partially constrained precipitates

TL;DR: In this paper, a finite element method was used to predict the region in the matrix in which radial hydride is likely to form and fracture, by taking into consideration grain-size, texture and multi-axial state of stress.
Journal ArticleDOI

Influence of hydride orientation on fracture toughness of CWSR Zr-2.5%Nb pressure tube material between RT and 300 °C

TL;DR: In this article, an experimental setup was designed, fabricated and used to form radial hydrides in Zr-2.5%Nb alloy pressure tube spool, which was loaded on a universal testing machine (UTM) fitted with an environmental chamber and subjected to a temperature cycle for the stress reorientation treatment.
Journal ArticleDOI

Evaluation of effect of hydrogen on toughness of Zircaloy-2 by instrumented drop weight impact testing

TL;DR: In this article, the degradation in fracture toughness of Zircaloy-2 was evaluated by carrying out instrumented drop-weight tests on curved Charpy specimens fabricated from virgin pressure tube.
Journal ArticleDOI

A combined SIF and temperature model of delayed hydride cracking in zirconium materials

TL;DR: In this paper, an integrated model of DHC which combines two independent calculation models is presented, the first calculation sub-model is designed to predict the critical characteristics of hydrides (their length and thickness) depending on both temperature and SIF.
Journal ArticleDOI

Material development for India’s nuclear power programme

TL;DR: A brief overview of the materials research activities currently being pursued at Bhabha Atomic Research Centre is presented in this article, where the focus is to provide materials, processes and processing solutions to the emerging needs of evolving indigenous nuclear energy systems by proactive research and development on a continuing basis.
References
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Journal ArticleDOI

Elastic and plastic accommodation effects on metal-hydride solubility☆

TL;DR: In this paper, a model that is capable of accounting for the hysteresis observed in the measured terminal solid solubilities (TSS) of metal hydride systems is presented.
Journal ArticleDOI

The terminal solid solubility of hydrogen and deuterium in Zr-2.5Nb alloys

TL;DR: In this article, the terminal solid solubility (TSS) of Zr alloys that are used in the nuclear industry is modeled as a function of temperature and the hysteresis between hydride dissolution and precipitation is studied.
Journal ArticleDOI

Environmentally-induced cracking of zirconium alloys — A review

TL;DR: The general field of environmentally-induced cracking of zirconium alloys has been reviewed and the phenomena that are observed and the progress in understanding the mechanisms are summarized in this article.
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Evolution of microstructure during fabrication of Zr-2.5 Wt pct Nb alloy pressure tubes

TL;DR: In this paper, a modified route involving hot extrusion followed by two pilgering operations with an intermediate annealing step was examined in detail, with the main aim of this work being to produce a microstructure and texture which are known to yield a lower irradiation growth.
Journal ArticleDOI

CANDU-PHW Pressure Tubes: Their Manufacture, Inspection, and Properties

TL;DR: In this article, cold-worked Zr-2.5 wt% Nb pressure tubes for Canada Deuterium Uranium Pressurized Heavy Water Reactors are made by hot extruding hollow billets into tubes that are cold worked to size and to develop their tensile strength.
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