Radiation Damage Exposure and Embrittlement of Reactor Pressure Vessels PDF Download
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Author: K. Shure
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 72
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Book Description
Author: K. Shure
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 72
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Book Description
Author: L. E. Steele
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 226
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Book Description
Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803104731
Category : Boiling water reactors
Languages : en
Pages : 303
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Book Description
Author: S. Seifert
Publisher:
ISBN:
Category : Damage correlation
Languages : en
Pages : 8
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Book Description
Experiments comparing the embrittling effects of high-energy (10-MeV) electrons and test reactor fast neutrons have been performed to elucidate the role of primary damage state on reactor pressure vessel embrittlement. Electrons produce displacement damage primarily by low-energy atomic recoils, while fast neutrons produce displacements from considerably higher energy recoils. Comparison of changes resulting from neutron irradiation, in which nascent point-defect clusters can form in dense cascades, with electron irradiation, where cascade formation is minimized, can provide insight into the role that the in-cascade point-defect clusters have on embrittlement mechanisms. Yield strength changes induced by 10-MeV electrons or test reactor neutron irradiations of unalloyed iron and an Fe-0.9 wt.% Cu-1.0 wt.% Mn alloy were examined up to 1.5 x 10-2 dpa. The small alloying additions substantially enhanced embrittlement in both the electron- and neutron-irradiated samples relative to unalloyed iron. Similar embrittlement trends with increasing radiation damage were observed for electrons and neutrons in both the ternary and unalloyed iron. Preliminary results of small-angle X-ray scattering measurements of embrittled microstructures are also reported.
Author: Naoki Soneda
Publisher: Elsevier
ISBN: 0857096478
Category : Technology & Engineering
Languages : en
Pages : 437
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Book Description
Reactor Pressure Vessels (RPVs) contain the fuel and therefore the reaction at the heart of nuclear power plants. They are a life-determining structural component: if they suffer serious damage, the continued operation of the plant is in jeopardy. This book critically reviews irradiation embrittlement, the main degradation mechanism affecting RPV steels, and mitigation routes for managing the RPV lifetime. Part I reviews RPV design and fabrication in different countries, with an emphasis on the materials required, their important properties, and manufacturing technologies. Part II then considers RVP embrittlement in operational nuclear power plants using different reactors. Chapters are devoted to embrittlement in light-water reactors, including WWER-type reactors and Magnox reactors. Finally, Part III presents techniques for studying embrittlement, including irradiation simulation techniques, microstructural characterisation techniques, and probabilistic fracture mechanics. Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants provides a thorough review of an issue that is central to the safety of nuclear power generation. The book includes contributions from an international team of experts, and will be a useful resource for nuclear plant operators and managers, relevant regulatory and safety bodies, nuclear metallurgists and other academics in this field Discusses reactor pressure vessel (RPV) design and the effect irradiation embrittlement can have, the main degradation mechanism affecting RPVs Examines embrittlement processes in RPVs in different reactor types, as well as techniques for studying RPV embrittlement
Author: GE. Lucas
Publisher:
ISBN:
Category : Embrittlement
Languages : en
Pages : 36
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Book Description
A model of irradiation embrittlement is described for predicting the 41-J Charpy V-notch temperature shifts (?T) as a function of metallurgical variables and neutron exposure conditions. This forecasting procedure combines semi-empirical physical models with statistical analyses of test and power reactor data, and calibration against data from fundamental experiments in which both mechanical property and microstructural changes are evaluated. The models are based on the evolution of a damage microstructure, which includes both copper precipitates and a radiation damage component enhanced by nickel. The precipitate volume is also increased by nickel and impurity phosphorus. Predicted hardening and shifts associated with these extended defects are based on empirically validated models. The model is able to self-consistently rationalize a wide array of microstructural and mechanical property data for commercial pressure vessel steels as well as model alloys.
Author: Lendell E. Steele
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 252
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Book Description
Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 9780803102637
Category : Technology & Engineering
Languages : en
Pages : 240
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Book Description
Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 9780803100664
Category : Freshwater microbiology
Languages : en
Pages : 269
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Book Description
Author: C. Z Serpan (Jr)
Publisher:
ISBN:
Category :
Languages : en
Pages : 23
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Book Description
The deleterious effect of high energy neutrons upon the mechanical properties of reactor pressure vessel steels has prompted the employment of material surveillance programs in many nuclear power plants. These programs provide for the exposure of test specimens representative of the reactor pressure vessel at in-reactor locations, wherein they will experience the same thermal and radiation damage history as the vessel itself. Evaluation of these specimens, which reveals the progressive changes in the mechanical properties of the vessel, provides a basis upon which operational procedures and maximum lifetime exposure may be formulated for the plant. A review and an analysis of several instances of shortcomings in surveillance programs are presented along with a set of recommendations for consideration in planning new surveillance programs. In utilizing these recommendations, pressure vessel surveillance programs can be made to provide valuable information for use in determining plant operations; at the same time results from these programs may add to the general knowledge of radiation effects in pressure vessel steels or other materials subject to radiation. Recognition of the value of surveillance programs and their conscientious application should further the public acceptance of nuclear reactors as safe alternative power systems.
