Neutron and Thermal Embrittlement of RPV Steels PDF Download
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Author: Randy K. Nanstad
Publisher:
ISBN:
Category : Embrittlement
Languages : en
Pages : 39
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Book Description
Because the reactor pressure vessel (RPV) represents the first structural line of defense against the release of radiation to the public, the design and fabrication of the RPV for any nuclear reactor facility is performed at very high standards in accordance with consensus codes that are based on mechanical and physical properties of the steels used to construct the vessel. Nuclear RPVs may weigh up to 800 tons with wall thicknesses up to approximately 330 mm and are clad on the inside with stainless-steel weld metal and given a final post-weld heat treatment. The RPV is a unique structural component in that it operates under high pressures and temperatures and is exposed to relatively high neutron radiation. Although typical RPV steels and welds have excellent fracture toughness at room temperature and above when put into service, the degrading effects of high-energy neutron irradiation can cause levels of irradiation-induced embrittlement in radiation-sensitive materials of concern for the structural integrity of the RPV. In recent decades, remarkable progress has been made in developing a mechanistic understanding of irradiation embrittlement. This progress includes developing physically based and statistically calibrated models of Charpy V-notch-indexed transition temperature shifts based on results from RPV surveillance programs complemented by significant results from comprehensive research experiments performed in test reactors. In addition, advances in elastic-plastic fracture mechanics allow for a relatively small number of relatively small specimens to characterize the fracture toughness of RPV steels with statistical confidence. This paper presents a review of the primary mechanical properties, test procedures, examples of applicable codes and standards, and specimen types used to characterize RPV steels and welds, the effects of neutron irradiation on those most relevant mechanical properties, and a brief review of the effects of thermal aging on RPV materials. The paper closes with a summary.
Author: Randy K. Nanstad
Publisher:
ISBN:
Category : Embrittlement
Languages : en
Pages : 39
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Book Description
Because the reactor pressure vessel (RPV) represents the first structural line of defense against the release of radiation to the public, the design and fabrication of the RPV for any nuclear reactor facility is performed at very high standards in accordance with consensus codes that are based on mechanical and physical properties of the steels used to construct the vessel. Nuclear RPVs may weigh up to 800 tons with wall thicknesses up to approximately 330 mm and are clad on the inside with stainless-steel weld metal and given a final post-weld heat treatment. The RPV is a unique structural component in that it operates under high pressures and temperatures and is exposed to relatively high neutron radiation. Although typical RPV steels and welds have excellent fracture toughness at room temperature and above when put into service, the degrading effects of high-energy neutron irradiation can cause levels of irradiation-induced embrittlement in radiation-sensitive materials of concern for the structural integrity of the RPV. In recent decades, remarkable progress has been made in developing a mechanistic understanding of irradiation embrittlement. This progress includes developing physically based and statistically calibrated models of Charpy V-notch-indexed transition temperature shifts based on results from RPV surveillance programs complemented by significant results from comprehensive research experiments performed in test reactors. In addition, advances in elastic-plastic fracture mechanics allow for a relatively small number of relatively small specimens to characterize the fracture toughness of RPV steels with statistical confidence. This paper presents a review of the primary mechanical properties, test procedures, examples of applicable codes and standards, and specimen types used to characterize RPV steels and welds, the effects of neutron irradiation on those most relevant mechanical properties, and a brief review of the effects of thermal aging on RPV materials. The paper closes with a summary.
Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803111878
Category : Fracture mechanics
Languages : en
Pages : 276
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Book Description
Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803114788
Category : Embrittlement
Languages : en
Pages : 405
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Book Description
Author: Lendell E. Steele
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 252
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Book Description
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: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803104731
Category : Boiling water reactors
Languages : en
Pages : 303
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6
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Book Description
As a result of observations of possible thermal embrittlement from recent studies with welds removed from retired steam generators of the Palisades Nuclear Plant (PNP), an assessment was made of thermal aging of reactor pressure vessel (RPV) steels under nominal reactor operating conditions. Discussions are presented on (1) data from the literature regarding relatively low-temperature thermal embrittlement of RPV steels; (2)relevant data from the US power reactor-embrittlement data base (PR-EDB); and (3)potential mechanisms of thermal embrittlement in low-alloy steels.
Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 9780803102637
Category : Technology & Engineering
Languages : en
Pages : 240
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Book Description
Author: A. L. Hiser
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 439
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Book Description
Neutron irradiation embrittlement of nuclear reactor pressure vessel (RPV) steels results in a loss of fracture toughness (e.g., reduction in load carrying capacity of the steel). For the setting of operational limits and assuring the continued safe operation of the plant, current procedures estimate the effects of neutron embrittlement using empirical relations or the results of small samples irradiated in the plant. These procedures account for uncertainties in the estimates through the use of margin terms to ensure the conservatism of the resultant estimate vis-a-vis the "real" material toughness. Therefore, the ability to develop non destructive measurements that can estimate the actual RPV steel fracture toughness in situ would provide more accurate evaluations of operating limits for plants. This study was undertaken to evaluate the suitability of ultrasonic attenuation measurements for estimating the fracture toughness of RPV steels. Ultrasonic measurements were made on samples in three distinct phases: (1) a heat treated RPV steel to induce changes in its fracture toughness; (2) several irradiated RPV steels to assess actual neutron embrittlement changes in fracture toughness; and (3) a matrix of unirradiated RPV steels with a range of as fabricated toughness levels. The results indicate that ultrasonic attenuation is generally able to identify differences in responses for samples with different toughness levels, although in some cases the differences in ultrasonic responses are small. The results from the three phases are not consistent, as in some cases reduced toughness results in higher attenuation and in other cases lower attenuation. This trend is not surprising given the different types of microstructural changes that result in the toughness changes for each phase of this work. In addition, different trends were identified for plate and weld materials.
Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 70
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Book Description
This publication sets out the findings of a co-ordinated research project to determine the influence of the mechanism of the deterioration effect in radiation embrittlement of reactor pressure vessel steels with a high nickel content in nuclear power plants, including procurement of materials, determination of mechanical properties, irradiation and testing of specimens, and microstructural characterisation.
