Stress-corrosion cracking of zircaloy in iodine; a probable failure mechanism in water reactor fuel pins PDF Download
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Author: A. Garlick
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: A. Garlick
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 53
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Book Description
A literature review and analysis were made of corrosion and degradation processes applicable to Zircaloy cladding on spent nuclear fuel in a tuff repository. In particular, lifetime sought for the Zircaloy is 10,000 years. Among the potential failure mechanisms examined were: oxidation by steam, air, and water, including the effects of ions whose presence is anticipated in the water; mechanical overload; stress (creep) rupture; stress-corrosion cracking (SCC); and delayed failure due to hydride cracking. The conclusion is that failure due to oxidation is not credible, although a few experiments are suggested to confirm the effect of aqueous fluoride on the Zircaloy cladding. Mechanical overload is not a problem, and failure from stress-rupture does not appear likely based on a modified Larson-Miller analysis. Analysis shows that delayed hydride cracking is not anticipated for the bulk of spent fuel pins. However, for a minority of pins under high stress, there is some uncertainty in the analysis as a result of: (1) uncertainty about crack depths in spent fuel claddings and (2) the effect of slow cooling on the formation of radially oriented hydride precipitates. Experimental resolution is called for. Finally, insufficient information is currently available on stress-corrosion cracking. While evidence is presented that SCC failure is not likely to occur, it is difficult to demonstrate this conclusively because the process is not clearly understood and data are limited. Further experimental work on SCC susceptibility is especially needed.
Author: A. J. Rothman
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 49
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Book Description
A literature review and analysis were made of corrosion and degradation processes applicable to Zircaloy cladding on spent nuclear fuel in a tuff repository. In particular, lifetime sought for the Zircaloy is 10,000 years. Among the potential failure mechanisms examined were: oxidation by steam, air, and water, including the effects of ions whose presence is anticipated in the water; mechanical overload; stress (creep) rupture; stress-corrosion cracking (SCC); and delayed failure due to hydride cracking. The conclusion is that failure due to oxidation is not credible, although a few experiments are suggested to confirm the effect of aqueous fluoride on the Zircaloy cladding. Mechanical overload is not a problem, and failure from stress-rupture does not appear likely based on a modified Larson-Miller analysis. Analysis shows that delayed hydride cracking is not anticipated for the bulk of spent fuel pins. However, for a minority of pins under high stress, there is some uncertainty in the analysis as a result of: (1) uncertainty about crack depths in spent fuel claddings and (2) the effect of slow cooling on the formation of radially oriented hydride precipitates. Experimental resolution is called for. Finally, insufficient information is currently available on stress-corrosion cracking. While evidence is presented that SCC failure is not likely to occur, it is difficult to demonstrate this conclusively because the process is not clearly understood and data are limited. Further experimental work on SCC susceptibility is especially needed.
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: L. Rouillon
Publisher:
ISBN:
Category : Deformation
Languages : en
Pages : 22
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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.
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 242
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Book Description
Author: L. Brunisholz
Publisher:
ISBN:
Category : Crack propagation
Languages : en
Pages : 17
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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.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1174
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 165
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Book Description
Author: Brent J. Lewis
Publisher: John Wiley & Sons
ISBN: 1119271495
Category : Science
Languages : en
Pages : 980
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Book Description
Fundamental of Nuclear Engineering is derived from over 25 years of teaching undergraduate and graduate courses on nuclear engineering. The material has been extensively class tested and provides the most comprehensive textbook and reference on the fundamentals of nuclear engineering. It includes a broad range of important areas in the nuclear engineering field; nuclear and atomic theory; nuclear reactor physics, design, control/dynamics, safety and thermal-hydraulics; nuclear fuel engineering; and health physics/radiation protection. It also includes the latest information that is missing in traditional texts, such as space radiation. The aim of the book is to provide a source for upper level undergraduate and graduate students studying nuclear engineering.
