Development of a Mechanistic Understanding of Radiation Embrittlement in Reactor Pressure Vessel Steels PDF Download
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Author:
Publisher:
ISBN:
Category : Electron microscopy
Languages : en
Pages : 75
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Author:
Publisher:
ISBN:
Category : Electron microscopy
Languages : en
Pages : 75
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Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803111878
Category : Fracture mechanics
Languages : en
Pages : 276
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Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 70
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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.
Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803104731
Category : Boiling water reactors
Languages : en
Pages : 303
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Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 9780803102637
Category : Technology & Engineering
Languages : en
Pages : 240
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Author: Lendell E. Steele
Publisher: ASTM International
ISBN: 0803114788
Category : Embrittlement
Languages : en
Pages : 405
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Book Description
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:
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ISBN:
Category :
Languages : en
Pages :
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Author: PN. Randall
Publisher:
ISBN:
Category : Annealing
Languages : en
Pages : 12
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This paper is in several parts: the first presents an overview of research activities sponsored by the U.S. Nuclear Regulatory Commission (NRC) on neutron irradiation embrittlement of pressure vessel steels. A series of irradiation experiments have evaluated effects of chemistry on the fracture toughness properties of submerged arc welds representing current nuclear vessel fabrication practices and provide data to validate ASME Code practices. A correlation between Charpy energy and fracture toughness is being studied as is a program on radiation sensitivity to define the role of dose rate and to study the effects of postirradiation heat treatment (annealing). The development of a comprehensive data base for radiation embrittlement data has been initiated and is being applied in a correlation of reactor surveillance data with test reactor data. A comprehensive dosimetry effort has produced validated standard methods for calculating and measuring neutron flux and fluence parameters and the correlation of these parameters to embrittlement of pressure vessel steels in light water reactors. Our knowledge of radiation damage to reactor vessels has also been greatly increased in recent years by the accumulation of power reactor surveillance data and by better models and better analysis techniques applied to that data. Unfortunately, the results show that radiation damage is often more than previously predicted, using Revision 1 of NRC Regulatory Guide 1.99, and will result in more restrictive pressure temperature limits. The second part of this paper describes some of the system and operational impacts produced, which in turn lead to challenges to long-established safety margins. Finally, a number of outstanding issues which require further research are discussed, many of which will require better understanding of radiation damage mechanisms.
Author: Lendell E. Steele
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 252
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