A Proposed Criterion for the Oxygen Embrittlement of Zircaloy-4 Fuel Cladding PDF Download
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Author: A. Sawatzky
Publisher:
ISBN:
Category : Embrittlement
Languages : en
Pages : 18
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Book Description
Under the condition postulated for a loss-of-coolant accident (LOCA), Zircaloy-4 fuel cladding may experience a temperature transient during which it absorbs an appreciable amount of oxygen from the coolant. Theoretical models for predicting cladding behavior during loss-of-coolant (LOC) are being developed, but until the failure mechanisms can be clearly established, an empirical criterion must be employed.
Author: A. Sawatzky
Publisher:
ISBN:
Category : Embrittlement
Languages : en
Pages : 18
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Book Description
Under the condition postulated for a loss-of-coolant accident (LOCA), Zircaloy-4 fuel cladding may experience a temperature transient during which it absorbs an appreciable amount of oxygen from the coolant. Theoretical models for predicting cladding behavior during loss-of-coolant (LOC) are being developed, but until the failure mechanisms can be clearly established, an empirical criterion must be employed.
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 627
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Book Description
Author: J. H. Schemel
Publisher: ASTM International
ISBN: 9780803106017
Category : Business & Economics
Languages : en
Pages : 656
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Book Description
Author: T. Furuta
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 13
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Book Description
To estimate the degree of conservatism of the present embrittlement criteria, the following examinations have been conducted. Zircaloy-4 tubes were oxidized at temperatures ranging from 1173 to 1573 K, and then compressed at 373 K to determine the embrittlement due to oxygen absorption. The simulated Zircaloy-clad fuel rods were burst and oxidized in steam at temperatures within the range 1200 to 1500 K. The segment sectioned from each burst cladding was also compressed to determine the effect of hydrogen absorption on cladding embrittlement. The results obtained from these experiments have revealed that the additional embrittlement due to hydrogen absorption is found to be significant in burst cladding.
Author: SL. Seiffert
Publisher:
ISBN:
Category : Embrittlement
Languages : en
Pages : 26
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Book Description
Author:
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 840
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Book Description
Author: D. Franklin
Publisher: ASTM International
ISBN: 9780803107540
Category : Business & Economics
Languages : en
Pages : 516
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Book Description
Author: HM. Chung
Publisher:
ISBN:
Category : Deformation
Languages : en
Pages : 28
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Book Description
To establish the mechanical response of Zircaloy cladding under thermal shock conditions typical of hypothetical loss-of-coolant accident (LOCA) situations in light-water reactors (LWRs), cladding specimens were ruptured in steam during transient heating (10 K/s), oxidized at maximum temperatures between 1140 and 1770 K for various times, and cooled from the isothermal oxidation temperature to ~1100 K at a rate of 5 K/s, and rapidly quenched by bottom flooding with water at a rate of ~0.05 m/s. Failure "maps" for fracture of the cladding by thermal shock were developed relative to the maximum oxidation temperature and various time-dependent oxidation parameters. In situ pendulum-load impact tests were conducted at room temperature on tubes that survived the thermal quench. Information on the total absorbed energy from these tests was correlated with more extensive results from instrumented drop-weight impact tests. The thermal shock results indicate that the present Zircaloy embrittlement criterion (that is, a total oxidation limit of 17 percent of the wall thickness and a maximum cladding temperature of 1477 K) is conservative and that a more quantitative criterion, based upon the mechanical behavior of the oxidized material, can be formulated with a specified degree of conservatism consistent with the mechanical loads imposed on the cladding during reflood and the maximum amount of oxidation set by the margin of performance of emergency core-cooling systems in LWRs.
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1364
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 136
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