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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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Citations
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Journal ArticleDOI

Delayed hydride cracking in Zr–2.5Nb pressure tube material: influence of fabrication routes

TL;DR: In this article, the delayed hydride cracking (DHC) velocity was measured for Zr-2.5Nb alloy pressure tubes manufactured from cold-worked and stress-relieved (CWSR) route and quenched and aged (Q&A) route at 162, 203, and 250
Journal ArticleDOI

Influence of hydrogen content on fracture toughness of CWSR Zr-2.5Nb pressure tube alloy

TL;DR: In this paper, the fracture toughness of unirradiated, cold worked and stress relieved (CWSR) Zr-2.5Nb pressure tube alloys used in Indian Pressurized Heavy Water Reactor is reported.
Journal ArticleDOI

Threshold stress intensity factor for delayed hydride cracking in Zr–2.5%Nb pressure tube alloy

TL;DR: In this paper, a single CT specimen was used to determine DHC velocity at a constant temperature for a range of stress intensity factor (K-1) obtained by load drop method, and the activation energy associated with DHC was observed to be 35.1 kJ/mol.
Journal ArticleDOI

Creep Behavior of Hydrogenated Zirconium Alloys

TL;DR: In this paper, the effect of hydrogen on the creep behavior of Zirconium alloys used in the water reactors is discussed and a detailed review of the effects of hydrogen in Zr alloys is presented.
Journal ArticleDOI

Evaluation of a delayed hydride cracking in Zr–2.5Nb CANDU and RBMK pressure tubes

TL;DR: In this paper, a delayed hydride cracking (DHC) was investigated using compact toughness specimens in order to determine the crack growth velocity in CANDU and RBMK Zr 2.5Nb pressure tubes under a constant loading, and different temperatures and different hydrogen contents.
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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