Author: J. C. Wood
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Effects of irradiation on the iodine-induced stress corrosion cracking of CANDU zircaloy fuel cladding
Author: J. C. Wood
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Iodine-Induced Stress Corrosion of Zircaloy Fuel Cladding
Author: L. Brunisholz
Publisher:
ISBN:
Category : Crack propagation
Languages : en
Pages : 17
Book Description
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.
Publisher:
ISBN:
Category : Crack propagation
Languages : en
Pages : 17
Book Description
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
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 165
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 165
Book Description
Effect of Zirconium Oxide on the Stress-Corrosion Susceptibility of Irradiated Zircaloy Cladding
Author: RF. Mattas
Publisher:
ISBN:
Category : Iodine
Languages : en
Pages : 13
Book Description
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.
Publisher:
ISBN:
Category : Iodine
Languages : en
Pages : 13
Book Description
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
Author: R. Sejnoha
Publisher: Philadelphia : American Society for Testing and Materials
ISBN:
Category :
Languages : en
Pages : 24
Book Description
Publisher: Philadelphia : American Society for Testing and Materials
ISBN:
Category :
Languages : en
Pages : 24
Book Description
Modeling of Zircaloy Stress-Corrosion Cracking
Author: RE. Einziger
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 32
Book Description
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.
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 32
Book Description
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
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 922
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 922
Book Description
Failure Mechanisms of Irradiated Zr Alloys Related to PCI
Author: L. Rouillon
Publisher:
ISBN:
Category : Deformation
Languages : en
Pages : 22
Book Description
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.
Publisher:
ISBN:
Category : Deformation
Languages : en
Pages : 22
Book Description
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
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 8
Book Description
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.
Publisher:
ISBN:
Category :
Languages : en
Pages : 8
Book Description
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
Author: B. A. Surette
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description