Modeling of Zircaloy Stress-Corrosion Cracking PDF Download
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Author: RE. Einziger
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 32
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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.
Author: RE. Einziger
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 32
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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.
Author: Lakshman Santanam
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 28
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Book Description
Two potential degradation mechanisms, creep and stress corrosion cracking, of Zircaloy cladding during repository storage of spent nuclear fuel have been investigated. The deformation and fracture map methodology has been used to predict maximum allowable initial storage temperatures to achieve a thousand year life without rupture as a function of spent-fuel history. A stress analysis of fuel rods has been performed. Stresses in the outer zirconium oxide layer and the inner Zircaloy tube have been predicted for typical internal pressurization, oxide layer thickness, volume expansion from formation of the oxide layer and thermal expansion coefficients of the cladding and oxide. Stress relaxation occurring in-reactor has also been taken into account. The calculations indicate that for the anticipated storage conditions investigated, the outer zirconium oxide layer is in a state of compression thus making it unlikely that stress corrosion cracking of the exterior surface will occur.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 28
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Book Description
Two potential degradation mechanisms, creep and stress corrosion cracking, of Zircaloy cladding during repository storage of spent nuclear fuel have been investigated. The deformation and fracture map methodology has been used to predict maximum allowable initial storage temperatures to achieve a thousand year life without rupture as a function of spent-fuel history. A stress analysis of fuel rods has been performed. Stresses in the outer zirconium oxide layer and the inner Zircaloy tube have been predicted for typical internal pressurization, oxide layer thickness, volume expansion from formation of the oxide layer and thermal expansion coefficients of the cladding and oxide. Stress relaxation occurring in-reactor has also been taken into account. The calculations indicate that for the anticipated storage conditions investigated, the outer zirconium oxide layer is in a state of compression thus making it unlikely that stress corrosion cracking of the exterior surface will occur. 20 refs., 6 figs., 9 tabs.
Author: A. K. Miller
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 162
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Book Description
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 849
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Book Description
Author: D. Cubicciotti
Publisher:
ISBN:
Category : Fission-product iodine
Languages : en
Pages : 21
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Book Description
A model for pellet-cladding interaction (PCI) fracture of light-water reactor (LWR) fuel rods is presented, the basis of which is that Zircaloy cladding fails by iodine stress corrosion cracking (SCC). Laboratory data on iodine SCC of irradiated Zircaloy provide the primary input to the model, but unirradiated Zircaloy SCC data and theoretical analyses are utilized to broaden the regime of validity to encompass the various power reactor observations.
Author: WR. Campbell
Publisher:
ISBN:
Category : Crack propagation
Languages : en
Pages : 20
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Book Description
A fracture mechanics model is presented for iodine-induced stress corrosion cracking in Zircaloy tubing. The model utilizes a power law to relate crack extension velocity to stress intensity factor, a hyperbolic tangent function for the influence of iodine concentration, and an exponential function for the influence of temperature and material strength. Comparisons of predicted to measured failure times show that predicted times are within a factor of two of the measured times for a majority of the specimens considered.
Author: Russell H. Jones
Publisher: ASM International(OH)
ISBN:
Category : Science
Languages : en
Pages : 466
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Book Description
Details the many conditions under which stress-corrosion cracking (SCC) can occur, the parameters which control SCC, and the methodologies for mitigating and testing for SCC, plus information on mechanisms of SCC with experimental data on a variety of materials. Contains information about environmen
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1144
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Book Description
