Irradiation Embrittlement of Reactor Pressure Vessels RPVs in Nuclear Power Plants

Book Irradiation Embrittlement of Reactor Pressure Vessels  RPVs  in Nuclear Power Plants Cover

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  • Publisher : Elsevier
  • Release : 01 September 2014
  • ISBN : 9780857096470
  • Page : 432 pages
  • Rating : 4.5/5 from 103 voters

Download Irradiation Embrittlement of Reactor Pressure Vessels RPVs in Nuclear Power Plants in PDF, Epub and Kindle

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

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Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants

Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants
  • Author : Naoki Soneda
  • Publisher : Elsevier
  • Release Date : 2014-09-01
  • ISBN : 9780857096470
GET THIS BOOKIrradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants

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

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels
  • Author : Lendell E. Steele
  • Publisher : ASTM International
  • Release Date : 1993
  • ISBN : 9780803114784
GET THIS BOOKRadiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels
  • Author : Lendell E. Steele
  • Publisher : ASTM International
  • Release Date : 1989
  • ISBN : 9780803111875
GET THIS BOOKRadiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels

Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels
  • Author : International Atomic Energy Agency
  • Publisher : IAEA
  • Release Date : 2005
  • ISBN : UOM:39015062419117
GET THIS BOOKEffects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels

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.

Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels

Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels
  • Author : Lendell E. Steele
  • Publisher : ASTM International
  • Release Date : 1983
  • ISBN : 0987654321XXX
GET THIS BOOKRadiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels

Long Term Irradiation Effects on the Mechanical Properties of Reactor Pressure Vessel Steels from Two Commercial PWR Plants

Long Term Irradiation Effects on the Mechanical Properties of Reactor Pressure Vessel Steels from Two Commercial PWR Plants
  • Author : Jenny Rouden,Pål Efsing,Martin Lundgren
  • Publisher : Unknown
  • Release Date : 2013
  • ISBN : OCLC:1251659761
GET THIS BOOKLong Term Irradiation Effects on the Mechanical Properties of Reactor Pressure Vessel Steels from Two Commercial PWR Plants

The Swedish nuclear power plants all have plant specific surveillance programs which includes samples from all relevant materials that are subjected to a fluence-level that exceeds 1*1017 n/cm2 over the estimated period of operation for the specific power plants. The Swedish pressurized water reactor (PWR)-plants are currently planning for a service period beyond 50 years of operation. As a portion of that, two of the three PWR units at the Ringhals site are conducting a major effort to verify the

Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region

Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region
  • Author : K. Sakamoto,S. Hatano,T. Osaki
  • Publisher : Unknown
  • Release Date : 2004
  • ISBN : OCLC:1251652458
GET THIS BOOKDevelopment of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region

In order to develop the integrity evaluation technology for aged major components of nuclear power plants, the Japan Power Engineering and Inspection Corporation (JAPEIC) has carried out the project named "Nuclear Power Plant Integrated Management Technology (PLIM)" entrusted by Japanese Ministry of Economy, Trade and Industry since 1996 Fiscal Year (FY). One of the objectives of this project is to establish the method for integrity evaluation of aged Japanese reactor pressure vessels (RPV) by developing the prediction equations of reduction of

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety
  • Author : International Atomic Energy Agency
  • Publisher : IAEA
  • Release Date : 2005
  • ISBN : UOM:39015062489078
GET THIS BOOKAssessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety

This report considers significant ageing mechanisms and degradation locations, as well as current practices for the assessment and management of the ageing of boiling water reactor (BWR) pressure vessels (RPVs). The report emphasises safety aspects and also provides information on current inspections, and monitoring and mitigation practices for managing ageing of BWR RPVs.

Overview of the Activities in Spain on Irradiation Embrittlement of RPV Steel

Overview of the Activities in Spain on Irradiation Embrittlement of RPV Steel
  • Author : A. Ballesteros,J. Bros
  • Publisher : Unknown
  • Release Date : 1994
  • ISBN : OCLC:1251668361
GET THIS BOOKOverview of the Activities in Spain on Irradiation Embrittlement of RPV Steel

Specific problems such as the embrittlement of the WER reactors or the integrity evaluation of the Yankee Rowe reactor pressure vessel, show the necessity of continuing in the understanding of the mechanisms responsible for the embrittlement. Besides, in order to increase the safety and performance of the nuclear power plants, it is important to optimize the surveillance programmes and develop the mitigation techniques of the damage caused by neutron radiation.

Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly

Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly
  • Author : Anonim
  • Publisher : Unknown
  • Release Date : 2015
  • ISBN : OCLC:946824351
GET THIS BOOKCrystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly

The integrity of reactor pressure vessels (RPVs) is of utmost importance to ensure safe operation of nuclear reactors under extended lifetime. Microstructure scale models at various length and time scales, coupled concurrently or through homogenization methods, can play a crucial role in understanding and quantifying irradiation induced defect production, growth and their influence on mechanical behavior of RPV steels. A multi-scale approach, involving atomistic, meso-and engineering scale models, is currently being pursued within the GRIZZLY project to understand and quantify

Structural Alloys for Nuclear Energy Applications

Structural Alloys for Nuclear Energy Applications
  • Author : Robert Odette,Steven Zinkle
  • Publisher : Newnes
  • Release Date : 2019-08-15
  • ISBN : 9780123973498
GET THIS BOOKStructural Alloys for Nuclear Energy Applications

High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL)

Heavy Component Replacement in Nuclear Power Plants

Heavy Component Replacement in Nuclear Power Plants
  • Author : International Atomic Energy Agency
  • Publisher : Unknown
  • Release Date : 2008
  • ISBN : 9201090080
GET THIS BOOKHeavy Component Replacement in Nuclear Power Plants

Component replacement is often the most feasible solution to solve the problems associated with primary water stress corrosion cracking of Alloy 600. Even if mitigation and/or repair were a local solution, replacement offers many advantages when addressing the assortment of potentially susceptible parts contained in a major component. This publication focuses on heavy components replacement considered strategic for nuclear power plant life management but not included in current maintenance activities carried out by utilities. The major and heavy components to

Comprehensive Nuclear Materials

Comprehensive Nuclear Materials
  • Author : Anonim
  • Publisher : Elsevier
  • Release Date : 2020-07-22
  • ISBN : 9780081028667
GET THIS BOOKComprehensive Nuclear Materials

Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (

Understanding and Mitigating Ageing in Nuclear Power Plants

Understanding and Mitigating Ageing in Nuclear Power Plants
  • Author : Philip G Tipping
  • Publisher : Elsevier
  • Release Date : 2010-10-26
  • ISBN : 9781845699956
GET THIS BOOKUnderstanding and Mitigating Ageing in Nuclear Power Plants

Plant life management (PLiM) is a methodology focussed on the safety-first management of nuclear power plants over their entire lifetime. It incorporates and builds upon the usual periodic safety reviews and licence renewals as part of an overall framework designed to assist plant operators and regulators in assessing the operating conditions of a nuclear power plant, and establishing the technical and economic requirements for safe, long-term operation. Understanding and mitigating ageing in nuclear power plants critically reviews the fundamental ageing-degradation

Application of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels

Application of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels
  • Author : AV. Nikolaeva,YA. Nikolaev
  • Publisher : Unknown
  • Release Date : 2000
  • ISBN : OCLC:1251647893
GET THIS BOOKApplication of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels

Radiation embrittlement and its mitigation by annealing of VVER-440 reactor pressure vessel steels are studied. The Russian regulatory approach for prediction of radiation embrittlement of VVER-440 steels is considered. Results of an investigation of materials cut out of operating nuclear power plants are discussed. Different models of re-irradiation embrittlement are compared. A new model for assessment of embrittlement under re-irradiation is developed.