Effects of irradiation on the iodine-induced stress corrosion cracking of CANDU zircaloy fuel cladding

Effects of irradiation on the iodine-induced stress corrosion cracking of CANDU zircaloy fuel cladding PDF Author: J. C. Wood
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Effects of irradiation on the iodine-induced stress corrosion cracking of CANDU zircaloy fuel cladding

Effects of irradiation on the iodine-induced stress corrosion cracking of CANDU zircaloy fuel cladding PDF Author: J. C. Wood
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Iodine-Induced Stress Corrosion of Zircaloy Fuel Cladding

Iodine-Induced Stress Corrosion of Zircaloy Fuel Cladding PDF Author: L. Brunisholz
Publisher:
ISBN:
Category : Crack propagation
Languages : en
Pages : 17

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Because of its impact on nuclear power plant reliability, fuel cladding failure induced by pellet cladding interaction is a problem of major concern. It is usually analyzed as stress corrosion cracking caused by volatile fission products like iodine.

Iodine induced stress corrosion cracking of Zircaloy fuel cladding materials

Iodine induced stress corrosion cracking of Zircaloy fuel cladding materials PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 165

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Effect of Zirconium Oxide on the Stress-Corrosion Susceptibility of Irradiated Zircaloy Cladding

Effect of Zirconium Oxide on the Stress-Corrosion Susceptibility of Irradiated Zircaloy Cladding PDF Author: RF. Mattas
Publisher:
ISBN:
Category : Iodine
Languages : en
Pages : 13

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Cladding specimens were obtained from two fuel rods irradiated in the Big Rock Point Reactor to a burnup of ~8 gigawatt days per ton. Both claddings had a uniform, thick (~4 μm) zirconium oxide layer on the inner surface. The significant difference between the two rods was the degree of fission-gas release (0.2 versus 14.3 percent). The high-gas-release rod contained a significantly greater amount of fission-product deposits, and, in some areas, breaks in the inner-surface oxide were observed. The cladding speciments, with the fuel removed, were subjected to stress-rupture tests in an iodine environment using internal gas pressurization to evaluate their stress corrosion cracking (SCC) susceptibility. All tests were conducted at an initial iodine concentration of 0.6 mg/cm2 and a temperature of 325°C. Specimens from the high-gas-release rod exhibited signifciantly increased susceptibility to iodine SCC, with a threshold stress level of ~200 MPa as compared with ~280 MPa in the specimens from the low-gas-release rod. The results suggest that the inner-surface oxide provides a barrier to iodine penetration. Hence, the thick unbreached oxide on the low-gas-release rod provided greater resistance to iodine SCC than the breached oxide on the high-gas-release rod.

Iodine-induced Stress Corrosion Cracking of Fixed Deflection Stressed Slotted Rings of Zircaloy Fuel Cladding

Iodine-induced Stress Corrosion Cracking of Fixed Deflection Stressed Slotted Rings of Zircaloy Fuel Cladding PDF Author: R. Sejnoha
Publisher: Philadelphia : American Society for Testing and Materials
ISBN:
Category :
Languages : en
Pages : 24

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Modeling of Zircaloy Stress-Corrosion Cracking

Modeling of Zircaloy Stress-Corrosion Cracking PDF Author: RE. Einziger
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 32

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A phenomenological model has been developed for predicting iodine-induced stress-corrosion crack (SCC) initiation and growth in Zircaloy cladding. This model is capable of predicting various observed behaviors related to SCC.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 922

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Failure Mechanisms of Irradiated Zr Alloys Related to PCI

Failure Mechanisms of Irradiated Zr Alloys Related to PCI PDF Author: L. Rouillon
Publisher:
ISBN:
Category : Deformation
Languages : en
Pages : 22

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The impact of irradiation damage accumulated in fuel claddings on their mechanical behavior and their susceptibility to iodine-induced stress corrosion cracking (I-SCC) was studied in irradiated zirconium and standard Zircaloy-4 sheets subjected to interrupted tension tests in methanol/iodine solutions and in an inert environment. The study of the I-SCC cracks has been carried out by SEM, while the characterization of the irradiation defects and the activated slip systems used TEM.

Reduced Yield Stress for Zirconium Exposed to Iodine

Reduced Yield Stress for Zirconium Exposed to Iodine PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 8

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Iodine-induced stress-corrosion cracking (ISCC), a known failure mode for nuclear fuel cladding, occurs when iodine generated during the irradiation of a nuclear fuel pellet escapes the pellet through diffusion or thermal cracking and chemically interacts with the inner surface of the clad material, inducing a subsequent effect on the cladding's resistance to mechanical stress. To complement experimental investigations of ISCC, a reactive force field (ReaxFF) compatible with the Zr-I chemical and materials systems has been developed and applied to simulate the impact of iodine exposure on the mechanical strength of the material. The study shows that the material's resistance to stress (as captured by the yield stress of a high-energy grain boundary) is related to the surface coverage of iodine, with the implication that ISCC is the result of adsorption-enhanced decohesion.

The effects of three different coatings on iodine-induced stress-corrosion cracking of zircaloy-4

The effects of three different coatings on iodine-induced stress-corrosion cracking of zircaloy-4 PDF Author: B. A. Surette
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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