Irradiation Growth in Annealed and 25% Cold-worked Zircaloy-2 Between 353-673K PDF Download
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Author: A. Rogerson
Publisher:
ISBN:
Category :
Languages : en
Pages : 13
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Author: A. Rogerson
Publisher:
ISBN:
Category :
Languages : en
Pages : 13
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Book Description
Author: A. Rogerson
Publisher:
ISBN:
Category :
Languages : en
Pages : 20
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Author: R. A. Murgatroyd
Publisher:
ISBN:
Category :
Languages : en
Pages : 10
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Author: K L Murty
Publisher: Elsevier
ISBN: 0857097458
Category : Technology & Engineering
Languages : en
Pages : 441
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Book Description
Light water reactors (LWRs) are the predominant class of nuclear power reactors in operation today; however, ageing and degradation can influence both their performance and lifetime. Knowledge of these factors is therefore critical to safe, continuous operation. Materials ageing and degradation in light water reactors provides a comprehensive guide to prevalent deterioration mechanisms, and the approaches used to handle their effects.Part one introduces fundamental ageing issues and degradation mechanisms. Beginning with an overview of ageing and degradation issues in LWRs, the book goes on to discuss corrosion in pressurized water reactors and creep deformation of materials in LWRs. Part two then considers materials’ ageing and degradation in specific LWR components. Applications of zirconium alloys in LWRs are discussed, along with the ageing of electric cables. Materials management strategies for LWRs are then the focus of part three. Materials management strategies for pressurized water reactors and VVER reactors are considered before the book concludes with a discussion of materials-related problems faced by LWR operators and corresponding research needs.With its distinguished editor and international team of expert contributors, Materials ageing and degradation in light water reactors is an authoritative review for anyone requiring an understanding of the performance and durability of this type of nuclear power plant, including plant operators and managers, nuclear metallurgists, governmental and regulatory safety bodies, and researchers, scientists and academics working in this area. Introduces the fundamental ageing issues and degradation mechanisms associated with this class of nuclear power reactors Considers materials ageing and degradation in specific light water reactor components, including properties, performance and inspection Chapters also focus on material management strategies
Author: J. H. Schemel
Publisher: ASTM International
ISBN: 9780803106017
Category : Business & Economics
Languages : en
Pages : 656
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Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 627
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Author: J. Walter Joseph
Publisher:
ISBN:
Category : Stress relaxation (Physics)
Languages : en
Pages : 28
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Author: RA. Holt
Publisher:
ISBN:
Category : Congress
Languages : en
Pages : 15
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Accelerating irradiation growth has been reported for several zirconium alloys with a range of metallurgical states during high-temperature tests in fast-breeder reactors (673 to 723 K) for annealed Zircaloys in thermal test reactors at power reactor temperatures (523 to 623 K) and in power reactor core components fabricated from annealed or recrystallized Zircaloy. In the latter case, there was a transition from low to high irradiation growth rates at moderate fluences (about 3 x 1025 n/m2, E > 1 MeV, at 580 K) related to the nucleation and growth of basal plane c-component loops.
Author: RB. Adamson
Publisher:
ISBN:
Category : Annealed
Languages : en
Pages : 27
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Book Description
Irradiation growth behavior of Zircaloy-2 and -4 was studied on specimens irradiated in the Experimental Breeder Reactor II to fluences of 1.4 to 6.3 x 1025 neutrons (n).m-2 (E > 1 MeV) in the temperature range 644 to 723 K. Measurements in the three principal directions on annealed and cold-worked/stress-relieved Zircaloy-2 slab materials provided evidence that growth is a constant-volume process up to about 680 K. The growth strains were shown to be determined by the crystallographic texture, that is, proportional to (1-3(1-3fdc)), where), where fdc is the fraction of basal poles, is the fraction of basal poles, fc, in the direction d. The growth strains for annealed and cold-worked Zircaloy were large relative to previously reported data, were similar in magnitude, were strongly dependent on irradiation temperature, and varied linearly with fluence over the range investigated. Transmission electron microscopy on annealed Zircaloy-4 specimens revealed a few small voids and larger cavities, a grain boundary second phase, and dislocation loops, tangles, and arrays. The high growth strains in annealed Zircaloy appear to be governed by dislocation arrays formed during irradiation. This implies a change in growth mechanism from that pertaining at lower temperatures in annealed material. The data suggest a transition from saturating steady-state growth at lower temperatures to increasing and eventually high steady-state rates under the conditions of these tests.
Author: A. Rogerson
Publisher:
ISBN:
Category :
Languages : en
Pages : 16
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