Oxidation and biaxial deformation behaviour of CANDU zircaloy-4 fuel cladding in air and steam environments in the temperature range 600-850 degrees c PDF Download
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Author: E. T. C. Ho
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ISBN:
Category :
Languages : en
Pages : 0
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Author: E. T. C. Ho
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: E. T. C. Ho
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author:
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ISBN:
Category :
Languages : en
Pages : 44
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There is little materials data on the oxidation and deformation behaviour of CANDU reactor Zircaloy-4 fuel cladding for temperatures from 673-1173 K, Data which is required in the analysis of a number of post-shutdown accident scenarios and fuel handling incidents in which the fuel bundles at low decay levels are postulated to heat up due to degraded cooling conditions. This report presents the results of a test program to study the oxidation and biaxial deformation behaviour of the fuel cladding material in an air environment at 873-1123 K. Tentative criteria and recommendations are included.
Author:
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Category :
Languages : en
Pages : 14
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Description of the major components and performance characteristics of theFuel Cladding Test Facility developed by Ontario Hydro Research Division.This facility willgenerate materials data on the oxidation and deformation behaviour of CANDUreactor Zircaloy-4 fuel cladding for temperatures in the range 673-1173K.Such data are needed in the analysis of some post-shutdown accident scenariosand fuel handling incidents.The test facility consists of: tube furnaces forspecimen heating under closed-loop control; apressurizing circuit for deformation under biaxial conditions; amicroprocessor-based data logger for data acquisition; and an elapsed timeindicator for time to failure monitoring.
![High-temperature Deformation and Rupture Behavior of Internally-pressurized Zircaloy-4 Cladding in Vacuum and Steam Enivronments. [LOCA Conditions]. PDF](https://books.google.com/books/content/images/frontcover/7fuywgEACAAJ?fife=w80-h100)
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Category :
Languages : en
Pages :
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The high-temperature diametral expansion and rupture behavior of Zircaloy-4 fuel-cladding tubes have been investigated in vacuum and steam environments under transient-heating conditions that are of interest in hypothetical loss-of-coolant accident situations in light-water reactors. The effects of internal pressure, heating rate, axial constraint, and localized temperature nonuniformities in the cladding on the maximum circumferential strain have been determined for burst temperatures between approximately 650 and 1350°C.
Author: Toshiyuki Yamashita
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ISBN:
Category : Fission products
Languages : en
Pages : 64
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Author: Kai Ping Chang
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Category :
Languages : en
Pages :
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Author: G. Montigny
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Category : Corrosion layer
Languages : en
Pages : 27
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During a loss-of-coolant accident (LOCA), the oxide layer grown during normal operations is expected to have a protective effect against high-temperature steam oxidation. However, with respect to post-quench ductility, such a barrier effect may be counterbalanced by a partial dissolution of the pre-oxide layer and associated diffusion of oxygen toward the metal. An extensive study has been carried out on the high-temperature oxidation behavior and post-quench mechanical properties of pre-oxidized Zircaloy-4. Cladding tubes have been pre-oxidized in oxygen environment at 425°C for increasing durations (up to 550 days), leading to pre-oxide layer thicknesses ranging from 7 to 65 ?m. All samples have been then subjected to high-temperature steam oxidation at 900°C, 1000°C, or 1200°C followed by water quenching. Metallographic examinations, micro-hardness measurements, mean hydrogen content measurements, ring compression tests, and EPMA oxygen profiles have then been performed. At 900°C and 1000°C, referring to weight gain, the protective efficiency of the pre-oxide layer grown at 425°C appears to depend on its thickness. The protective effect is significant for 20 - to 40-?m pre-oxide thicknesses. Above 40 ?m, a partial loss of protectiveness is observed, associated to a significant hydrogen pickup. Thus, mechanical properties of such pre-oxidized claddings are highly degraded compared to an initially bare cladding undergoing a LOCA transient for which post-test ductility is maintained. At 1200°C, at similar oxidation durations, weight gains decrease continuously as the pre-oxide layer thickness increases. Thus, the pre-oxide can be viewed as partially protective; however, post-quench ductility is not improved compared to initially bare claddings.
Author: Charles W. Solbrig
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Category : Science
Languages : en
Pages :
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This chapter analyzes the effects of oxidation, embrittlement, and cladding growth on the Zircaloy-3 alloy used for 25 mil thick TREAT fuel assembly cladding. The fuel cladding is a protective shell which is used to prevent damage to the enclosed fuel. Therefore, its integrity is important to guarantee this protection. The above three factors which can affect the Zircaloy-3 cladding are considered in this chapter and investigated. Limits to operation are determined. The oxidation of Zircaloy-3 in air is of interest to air-cooled reactors and Zircaloy-2 and 4 for accidents in fuel storage pools. The temperature range of interest is from room temperature where the fuel is stored for long periods of time, through the temperature range encountered in normal operation (400 to 600°C) to the highest temperatures which are possible in extreme accident situations. This temperature range is considered in this chapter to be from room temperature to 1200°C.
Author: J. T. Prater
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ISBN:
Category : Oxidation
Languages : en
Pages : 22
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