Irradiation Accelerated Corrosion Of Reactor Core Materials Final Report
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Irradiation Accelerated Corrosion Of Reactor Core Materials Final Report
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Author :
language : en
Publisher:
Release Date : 2015
Irradiation Accelerated Corrosion Of Reactor Core Materials Final Report written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2015 with categories.
This project aims to understand how radiation accelerates corrosion of reactor core materials. The combination of high temperature, chemically aggressive coolants, a high radiation flux and mechanical stress poses a major challenge for the life extension of current light water reactors, as well as the success of most all GenIV concepts. Of these four drivers, the combination of radiation and corrosion places the most severe demands on materials, for which an understanding of the fundamental science is simply absent. Only a few experiments have been conducted to understand how corrosion occurs under irradiation, yet the limited data indicates that the effect is large; irradiation causes order of magnitude increases in corrosion rates. Without a firm understanding of the mechanisms by which radiation and corrosion interact in film formation, growth, breakdown and repair, the extension of the current LWR fleet beyond 60 years and the success of advanced nuclear energy systems are questionable. The proposed work will address the process of irradiation-accelerated corrosion that is important to all current and advanced reactor designs, but remains very poorly understood. An improved understanding of the role of irradiation in the corrosion process will provide the community with the tools to develop predictive models for in-reactor corrosion, and to address specific, important forms of corrosion such as irradiation assisted stress corrosion cracking.
Irradiation Accelerated Corrosion Of Reactor Core Materials
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Author :
language : en
Publisher:
Release Date : 2015
Irradiation Accelerated Corrosion Of Reactor Core Materials written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2015 with categories.
This project aims to understand how radiation accelerates corrosion of reactor core materials. The combination of high temperature, chemically aggressive coolants, a high radiation flux and mechanical stress poses a major challenge for the life extension of current light water reactors, as well as the success of most all GenIV concepts. Of these four drivers, the combination of radiation and corrosion places the most severe demands on materials, for which an understanding of the fundamental science is simply absent. Only a few experiments have been conducted to understand how corrosion occurs under irradiation, yet the limited data indicates that the effect is large; irradiation causes order of magnitude increases in corrosion rates. Without a firm understanding of the mechanisms by which radiation and corrosion interact in film formation, growth, breakdown and repair, the extension of the current LWR fleet beyond 60 years and the success of advanced nuclear energy systems are questionable. The proposed work will address the process of irradiation-accelerated corrosion that is important to all current and advanced reactor designs, but remains very poorly understood. An improved understanding of the role of irradiation in the corrosion process will provide the community with the tools to develop predictive models for in-reactor corrosion, and to address specific, important forms of corrosion such as irradiation assisted stress corrosion cracking.
Reactor Core Materials
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Author :
language : en
Publisher:
Release Date : 1962
Reactor Core Materials written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1962 with Nuclear reactors categories.
Reactor Core Materials
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Author :
language : en
Publisher:
Release Date : 1958
Reactor Core Materials written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1958 with Nuclear reactors categories.
Irradiation Behaviour Of Metallic Materials For Fast Reactor Core Components
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Author :
language : ru
Publisher:
Release Date : 1979
Irradiation Behaviour Of Metallic Materials For Fast Reactor Core Components written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1979 with Fast reactors categories.
Irradiation Programs And Test Plans To Assess High Fluence Irradiation Assisted Stress Corrosion Cracking Susceptibility
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Author :
language : en
Publisher:
Release Date : 2015
Irradiation Programs And Test Plans To Assess High Fluence Irradiation Assisted Stress Corrosion Cracking Susceptibility written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2015 with categories.
. Irradiation assisted stress corrosion cracking (IASCC) is a known issue in current reactors. In a 60 year lifetime, reactor core internals may experience fluence levels up to 15 dpa for boiling water reactors (BWR) and 100+ dpa for pressurized water reactors (PWR). To support a safe operation of our fleet of reactors and maintain their economic viability it is important to be able to predict any evolution of material behaviors as reactors age and therefore fluence accumulated by reactor core component increases. For PWR reactors, the difficulty to predict high fluence behavior comes from the fact that there is not a consensus of the mechanism of IASCC and that little data is available. It is however possible to use the current state of knowledge on the evolution of irradiated microstructure and on the processes that influences IASCC to emit hypotheses. This report identifies several potential changes in microstructure and proposes to identify their potential impact of IASCC. The susceptibility of a component to high fluence IASCC is considered to not only depends on the intrinsic IASCC susceptibility of the component due to radiation effects on the material but to also be related to the evolution of the loading history of the material and interaction with the environment as total fluence increases. Single variation type experiments are proposed to be performed with materials that are representative of PWR condition and with materials irradiated in other conditions. To address the lack of IASCC propagation and initiation data generated with material irradiated in PWR condition, it is proposed to investigate the effect of spectrum and flux rate on the evolution of microstructure. A long term irradiation, aimed to generate a well-controlled irradiation history on a set on selected materials is also proposed for consideration. For BWR, the study of available data permitted to identify an area of concern for long term performance of component. The efficiency of hydrogen water chemistry mitigation technology may decrease as fluence increases for high-stress intensity factors. This report describes a program plan to determine the efficiency of hydrogen water chemistry as a function of the stress intensity factor applied and fluence. The use of existing, available, materials and the generation of additional materials via irradiation in a research reactor are considered.
Annual Report High Temperature Materials And Reactor Component Development Programs
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Author :
language : en
Publisher:
Release Date : 1965-02-26
Annual Report High Temperature Materials And Reactor Component Development Programs written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1965-02-26 with Heat resistant alloys categories.
Effects Of Radiation On Materials
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Author : Martin L. Grossbeck
language : en
Publisher: ASTM International
Release Date : 2004
Effects Of Radiation On Materials written by Martin L. Grossbeck and has been published by ASTM International this book supported file pdf, txt, epub, kindle and other format this book has been release on 2004 with Materials categories.
Reprocessing Of Irradiated Fission Reactor Fuel And Breeding Materials
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Author :
language : en
Publisher:
Release Date : 1958
Reprocessing Of Irradiated Fission Reactor Fuel And Breeding Materials written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1958 with Nuclear fuels categories.
Irradiation Effects On Structural Alloys For Nuclear Reactor Applications
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Author : A. L. Bement
language : en
Publisher: ASTM International
Release Date : 1971
Irradiation Effects On Structural Alloys For Nuclear Reactor Applications written by A. L. Bement and has been published by ASTM International this book supported file pdf, txt, epub, kindle and other format this book has been release on 1971 with Neutron flux categories.