Susceptibility of Zirconium Alloys to Delayed Hydrogen Cracking PDF Download

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Susceptibility of Zirconium Alloys to Delayed Hydrogen Cracking

Susceptibility of Zirconium Alloys to Delayed Hydrogen Cracking PDF Author: JFR Ambler
Publisher:
ISBN:
Category : Crack initiation
Languages : en
Pages : 19

Book Description
Smooth and notched cantilever beams and round-notched bars were machined from pressure tubes of cold-worked Zr-2.5Nb and Zircaloy-2. They were loaded in the temperature range 290 to 520 K. After two thermal cycles and at high stress, cracks were initiated in smooth beams of cold-worked Zr-2.5Nb. Under the same test conditions, cold-worked Zircaloy-2 plastically deformed with no cracking. When notches were present, cracks propagated at the same rate in both materials by delayed hydrogen cracking. In cold-worked Zr-2.5Nb, the crack velocity followed an Arrhenius plot with an apparent activation energy of 42 kJ/mol. Below 420 K, the threshold stress intensity factor for delayed hydrogen cracking was about 5 MPa m. Therefore, cracking can be prevented by keeping tensile stresses very low.

Susceptibility of Zirconium Alloys to Delayed Hydrogen Cracking

Susceptibility of Zirconium Alloys to Delayed Hydrogen Cracking PDF Author: JFR Ambler
Publisher:
ISBN:
Category : Crack initiation
Languages : en
Pages : 19

Book Description
Smooth and notched cantilever beams and round-notched bars were machined from pressure tubes of cold-worked Zr-2.5Nb and Zircaloy-2. They were loaded in the temperature range 290 to 520 K. After two thermal cycles and at high stress, cracks were initiated in smooth beams of cold-worked Zr-2.5Nb. Under the same test conditions, cold-worked Zircaloy-2 plastically deformed with no cracking. When notches were present, cracks propagated at the same rate in both materials by delayed hydrogen cracking. In cold-worked Zr-2.5Nb, the crack velocity followed an Arrhenius plot with an apparent activation energy of 42 kJ/mol. Below 420 K, the threshold stress intensity factor for delayed hydrogen cracking was about 5 MPa m. Therefore, cracking can be prevented by keeping tensile stresses very low.

Susceptibility of zirconium alloys to delayed hydrogen cracking

Susceptibility of zirconium alloys to delayed hydrogen cracking PDF Author: C. E. Coleman
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


Susceptibility of zirconium alloys to delayed hydrogen embrittlement

Susceptibility of zirconium alloys to delayed hydrogen embrittlement PDF Author: C. E. Ells
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


Susceptibility of Cold-worked Zirconium-2.5 WT% Niobium Alloy to Delayed Hydrogen Cracking

Susceptibility of Cold-worked Zirconium-2.5 WT% Niobium Alloy to Delayed Hydrogen Cracking PDF Author: C. E. Coleman
Publisher: Chalk River, Ont. : Metallurgical Engineering Branch, Chalk River Nuclear Laboratories
ISBN:
Category :
Languages : en
Pages : 25

Book Description


Susceptibility of Cold-worked Zirconium-2.5 WT% Nobium Alloy to Delayed Hydrogen Cracking

Susceptibility of Cold-worked Zirconium-2.5 WT% Nobium Alloy to Delayed Hydrogen Cracking PDF Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: ASTM Committee B-10 on Reactive and Refractory Metals and Alloys
Publisher: ASTM International
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 694

Book Description


Susceptibility of cold-worked zirconium-2.5 wt per cent niobium alloy to delayed hydrogen cracking

Susceptibility of cold-worked zirconium-2.5 wt per cent niobium alloy to delayed hydrogen cracking PDF Author: C. E. Coleman
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891

Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124996
Category : Microstructure
Languages : en
Pages : 953

Book Description


Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962

Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
The extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress was investigated. Susceptibility to time-dependent fracture was evaluated for unalloyed zirconium and Zircaloy-2 with 200 and 500 ppm hydrogen as well as for an experimental Zr Al-Sn-Mo alloy and the Canadian Zr-2.5Nb cladding material. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no room-temperature, timedependent fracture occurred which could be definitely attributed to the delayed failure phenomenon; an increased grain size, 20% cold deformation by rolling, or corrosion in 750 deg F steam did not significantly affect this behavior. The curve of applied stress versus time to failure at room temperature for the high-strength Zr-Al-Sn--Mo alloy containing 500 ppm hydrcgen established a strong susceptibility to delayed failure due to hydrogen absorption; studies on vacuum-annealed material showed no failures. Further, reduced temperature indicated that the occurrence of static fatigue is temperature dependent. Data for heattreated Zr 2.5Nb containing 500 ppm hydrogen indicated that this material is moderately sensitive to delayed failure at room temperature; higher hydrogen contents caused a greatly increased susceptibility to time-dependent fracture. (auth).