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
Publsiher: Elsevier
Total Pages: 432
Release: 2014-09-01
ISBN 10: 0857096478
ISBN 13: 9780857096470
Language: EN, FR, DE, ES & NL

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

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

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels
Author: Lendell E. Steele
Publsiher: ASTM International
Total Pages: 408
Release: 1993-01-01
ISBN 10: 9780803114784
ISBN 13: 0803114788
Language: EN, FR, DE, ES & NL

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels Book Review:

Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels

Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels
Author: Lendell E. Steele
Publsiher: ASTM International
Total Pages: 220
Release: 1983
ISBN 10:
ISBN 13:
Language: EN, FR, DE, ES & NL

Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels Book Review:

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
Publsiher: IAEA
Total Pages: 57
Release: 2005
ISBN 10:
ISBN 13: UOM:39015062419117
Language: EN, FR, DE, ES & NL

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

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.

Guidelines for Prediction of Irradiation Embrittlement of Operating WWER 440 Reactor Pressure Vessels

Guidelines for Prediction of Irradiation Embrittlement of Operating WWER 440 Reactor Pressure Vessels
Author: International Atomic Energy Agency
Publsiher: IAEA
Total Pages: 69
Release: 2005
ISBN 10:
ISBN 13: UOM:39015062418994
Language: EN, FR, DE, ES & NL

Guidelines for Prediction of Irradiation Embrittlement of Operating WWER 440 Reactor Pressure Vessels Book Review:

The IAEA International Database on RPV Materials (IDRPVM) is used for prediction and analysis of radiation embrittlement of WWER-440 reactor pressure vessel (RPV) materials. These guidelines will be used for assessment of irradiation embrittlement of RPV ferritic materials as a result of degradation during operation. Two approaches, i.e. transition temperatures based on Charpy impact notch toughness as well as those based on static fracture toughness tests, are used to develop the prediction formulas for radiation embrittlement of RPVs of WWER-440 nuclear power plants.--Publisher description.

Long Term Irradiation Phenomena in RPV Steels The LONGLIFE Project

Long Term Irradiation Phenomena in RPV Steels  The LONGLIFE Project
Author: Hieronymus Hein,Eberhard Altstadt,Frank Bergner
Publsiher: Unknown
Total Pages: 17
Release: 2013
ISBN 10:
ISBN 13: OCLC:1251646291
Language: EN, FR, DE, ES & NL

Long Term Irradiation Phenomena in RPV Steels The LONGLIFE Project Book Review:

The increasing age of European nuclear power plants and envisaged extensions of reactor pressure vessel (RPV) lifetimes up to 80 years require the accurate prediction and management of RPV neutron irradiation embrittlement. LONGLIFE ("Treatment of long term irradiation embrittlement effects in RPV safety assessment") is a collaborative project of the seventh Framework Programme of EURATOM. This project has been initiated as the next step forward towards obtaining an improved understanding of irradiation effects in RPV steels under conditions representative of long term operation (LTO) of RPVs. Phenomena that might become important at high neutron fluences (such as late-blooming effects and flux effects) must be considered in detail as part of the process of upgrading safety assessments and embrittlement surveillance procedures to underwrite the safety of LTO of RPVs. The work starts with the collection and evaluation of plant-specific information and data, such as target neutron fluences for LTO and the chemical compositions of the materials. This includes a survey of available results of RPV materials data from decommissioned plants of validating surveillance data and specific irradiation effects relevant for LTO. Microstructural data are obtained from different techniques with the aim of assessing the adequacy of current dose-damage models with respect to their relevance to the mechanisms of irradiation damage associated with LTO of RPVs. Complementary mechanical tests are performed in order to address gaps in existing experimental data. Microstructural data pertaining to the evolution of irradiation damage are correlated with changes in mechanical properties, and the most important influencing factors will be identified. Surveillance guidelines for LTO of RPV base materials and welds will be developed as one of the principal outputs of the project. The scope of work and the project structure are outlined in the paper. Two LTO relevant phenomena--late blooming effect and flux effect--are discussed in more detail.

Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly

Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly
Author: Anonim
Publsiher: Unknown
Total Pages: 24
Release: 2015
ISBN 10:
ISBN 13: OCLC:946824351
Language: EN, FR, DE, ES & NL

Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly Book Review:

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 irradiation induced embrittlement of RPV steels. Within this framework, a dislocation-density based crystal plasticity model has been de- veloped in GRIZZLY that captures the effect of irradation induced defects on the flow stress behavior and is presented in this report. The present formulation accounts for the interaction between self-interstitial loops and matrix dislocations. The model predictions have been validated with experiments and disloca- tion dynamics simulation.

Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity in Nuclear Power Plants

Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity in Nuclear Power Plants
Author: International Atomic Energy Agency
Publsiher: IAEA
Total Pages: 105
Release: 2005
ISBN 10:
ISBN 13: UOM:39015060992628
Language: EN, FR, DE, ES & NL

Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity in Nuclear Power Plants Book Review:

The master curve approach for assessing the fracture toughness of a sampled irradiated material has been gaining acceptance throughout the world. This direct measurement approach is preferred over the correlative and indirect methods used in the past to assess irradiated reactor pressure vessel (RPV) integrity. The master curve methodology already has been or is being assimilated into the ASME Boiler and Pressure Vessel Code, ASTM standards, USNRC regulations, German regulations (KTA 3203), IAEA PTS guidelines for WWER reactors as well as the VERLIFE "Unified Procedure for WWER Component Lifetime Assessment" and other industry guidance documents governing RPV integrity analysis. As this report was prepared using the results of many research projects and experiments, these guidelines for application will be used for a long time to evaluate and assess the residual life of 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
Publsiher: Unknown
Total Pages: 8
Release: 1994
ISBN 10:
ISBN 13: OCLC:1251668361
Language: EN, FR, DE, ES & NL

Overview of the Activities in Spain on Irradiation Embrittlement of RPV Steel Book Review:

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.

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
Publsiher: IAEA
Total Pages: 117
Release: 2005
ISBN 10:
ISBN 13: UOM:39015062489078
Language: EN, FR, DE, ES & NL

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

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.

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
Publsiher: Unknown
Total Pages: 11
Release: 2004
ISBN 10:
ISBN 13: OCLC:1251652458
Language: EN, FR, DE, ES & NL

Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region Book Review:

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 Charpy V-notch upper shelf energy (USE) due to neutron irradiation embrittlement and the correlation equations between USE and fracture toughness. In order to study the effect of certain chemical elements, such as Cu, Ni, P and Si, and initial USE on irradiation embrittlement, nine kinds of base metal, four kinds of weld metal and one kind of heat affected zone were prepared as test materials. They were irradiated at the OECD Halden test reactor, at three fluence levels (3, 6 and 10x1019n/cm2: E>1MeV) considering total fluence estimated after 48 Effective Full Power Year (EFPY) operation of Japanese PWR plants (2 and 3 loop). Post irradiation Charpy impact tests at the upper shelf region were completed to date. This paper is an interim test report about the reduction of USE in the high fluence region.

Radiation Damage of Structural Materials

Radiation Damage of Structural Materials
Author: J. Koutský,J. Kocík
Publsiher: Elsevier
Total Pages: 362
Release: 2013-10-22
ISBN 10: 1483291626
ISBN 13: 9781483291628
Language: EN, FR, DE, ES & NL

Radiation Damage of Structural Materials Book Review:

Maintaining the integrity of nuclear power plants is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on materials used in VVER-type nuclear reactors: Cr-Mo-V and Cr-Ni-Mo-V steel for RPV and Zr-Nb alloys for fuel element cladding. The book is divided into 7 main chapters, with the exception of the opening one and the chapter providing a phenomenological background for the subject of radiation damage. Chapters 3-6 are devoted to RPV steels and chapters 7-9 to zirconium alloys, analysing their radiation damage structure, changes of mechanical properties due to neutron irradiation as well as factors influencing the degree of their performance degradation. The recovery of damaged materials is also discussed. Considerable attention is paid to a comparison of VVER-type and western-type light-water materials. This monograph will be of great value to postgraduate students in nuclear engineering and materials science, and for designers and research workers in nuclear energy.

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
Publsiher: Unknown
Total Pages: 17
Release: 2013
ISBN 10:
ISBN 13: OCLC:1251659761
Language: EN, FR, DE, ES & NL

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

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 fitness to service of the reactor pressure vessel (RPV). In this case it is the weld in the belt-line region of the RPV, which is the apparent limiting factor. The weld metal contains high Nickel and high Manganese levels, not commonly used in other PWR-reactors. The effort includes a densified testing of the available surveillance capsule material in order to better understand the degradation phenomena and also an extended testing scope. A spin off effect of this program is that high fluence data for the base material also is made available from the testing. The chemical composition of the base metal is valid for many of the currently operating PWR-vessels. This study is an analysis of both the weld and the base material data extracted from the surveillance program. The results are evaluated against currently available data and correlation curves. In general, the results point out that the current Regulatory Guide 1.99 revision 2-correlation regarding the prediction of as-irradiated transition temperature is under-conservative for the tested material. The transition temperature shift, here evaluated as the temperature shift at 41J, is under-predicted by the correlation by as much as 70°C in some cases and increases with increasing fluences. However, prediction made by the French average irradiation embrittlement prediction formula, FIM-formula, is consistently better but still slightly under conservative.

Understanding and Mitigating Ageing in Nuclear Power Plants

Understanding and Mitigating Ageing in Nuclear Power Plants
Author: Philip G Tipping
Publsiher: Elsevier
Total Pages: 944
Release: 2010-10-26
ISBN 10: 1845699955
ISBN 13: 9781845699956
Language: EN, FR, DE, ES & NL

Understanding and Mitigating Ageing in Nuclear Power Plants Book Review:

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 mechanisms of materials used in nuclear power plant structures, systems and components (SSC), along with their relevant analysis and mitigation paths, as well as reactor-type specific PLiM practices. Obsolescence and other less obvious ageing-related aspects in nuclear power plant operation are also examined in depth. Part one introduces the reader to the role of nuclear power in the global energy mix, and the importance and relevance of plant life management for the safety regulation and economics of nuclear power plants. Key ageing degradation mechanisms and their effects in nuclear power plant systems, structures and components are reviewed in part two, along with routes taken to characterise and analyse the ageing of materials and to mitigate or eliminate ageing degradation effects. Part three reviews analysis, monitoring and modelling techniques applicable to the study of nuclear power plant materials, as well as the application of advanced systems, structures and components in nuclear power plants. Finally, Part IV reviews the particular ageing degradation issues, plant designs, and application of plant life management (PLiM) practices in a range of commercial nuclear reactor types. With its distinguished international team of contributors, Understanding and mitigating ageing in nuclear power plants is a standard reference for all nuclear plant designers, operators, and nuclear safety and materials professionals and researchers. Introduces the reader to the role of nuclear power in the global energy mix Reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC) Examines topics including elimination of ageing effects, plant design, and the application of plant life management (PLiM) practices in a range of commercial nuclear reactor types

Models for Embrittlement Recovery Due to Annealing of Reactor Pressure Vessel Steels

Models for Embrittlement Recovery Due to Annealing of Reactor Pressure Vessel Steels
Author: Anonim
Publsiher: Unknown
Total Pages: 69
Release: 1995
ISBN 10:
ISBN 13: OCLC:32906917
Language: EN, FR, DE, ES & NL

Models for Embrittlement Recovery Due to Annealing of Reactor Pressure Vessel Steels Book Review:

Consequence Evaluation of Radiation Embrittlement of Trojan Reactor Pressure Vessel Supports

Consequence Evaluation of Radiation Embrittlement of Trojan Reactor Pressure Vessel Supports
Author: Anonim
Publsiher: Unknown
Total Pages: 329
Release: 1990
ISBN 10:
ISBN 13: OCLC:23188066
Language: EN, FR, DE, ES & NL

Consequence Evaluation of Radiation Embrittlement of Trojan Reactor Pressure Vessel Supports Book Review:

Integrity of Reactor Pressure Vessels in Nuclear Power Plants

Integrity of Reactor Pressure Vessels in Nuclear Power Plants
Author: International Atomic Energy Agency
Publsiher: Unknown
Total Pages: 144
Release: 2009
ISBN 10: 9789201017093
ISBN 13: 920101709X
Language: EN, FR, DE, ES & NL

Integrity of Reactor Pressure Vessels in Nuclear Power Plants Book Review:

This publication is intended to assist nuclear utilities in optimising the service life of nuclear power plants. It reviews the latest research on the effects of neutron irradiation on the steels and welds of reactor pressure vessels within light water cooled and moderated reactors.

The LONGLIFE European Approach for Long Term Operation

The LONGLIFE European Approach for Long Term Operation
Author: Antonio Ballesteros Avila
Publsiher: Unknown
Total Pages: 10
Release: 2018
ISBN 10:
ISBN 13: OCLC:1251646154
Language: EN, FR, DE, ES & NL

The LONGLIFE European Approach for Long Term Operation Book Review:

An overview of the long-term operation (LTO) conditions in European nuclear power plants is presented herein together with recommendations for the reactor pressure vessel (RPV) surveillance programs based on the work performed in the international project LONGLIFE (Treatment of Long-Term Irradiation Embrittlement Effects in RPV Safety Assessment). Surveillance guidelines were developed in this project to support the potential end users (utilities, nuclear power plants, research organizations, etc.) in selecting the appropriate strategy and technical approaches for RPV irradiation surveillance for LTO, thus contributing to a reliable monitoring of the long-term irradiation effects in RPV and supporting the European efforts toward harmonizing procedures for RPV surveillance and safety assessment.

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
Publsiher: Unknown
Total Pages: 11
Release: 2000
ISBN 10:
ISBN 13: OCLC:1251647893
Language: EN, FR, DE, ES & NL

Application of the Floating Curve Model for Estimation of Re Irradiation Embrittlement of VVER 440 RPV Steels Book Review:

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.

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

Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels  IAEA TECDOC Series
Author: IAEA.
Publsiher: Unknown
Total Pages: 64
Release: 2005
ISBN 10:
ISBN 13: OCLC:1027149348
Language: EN, FR, DE, ES & NL

Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels IAEA TECDOC Series Book Review:

The goal of this publication was to investigate and understand the mechanism of the deterioration effect in radiation embrittlement of reactor pressure vessel steels of Ni.-Cr-Mo-V or Mn-Ni-Cr-Mo types with a high nickel content (>1.5 wt%) in nuclear power plants. Eleven institutes from eight different countries and the European Union participated in the Coordinated Research Project (CRP) entitled "Mechanism of Nickel Effect in Radiation Embrittlement of RPV Material", and six institutes conducted the irradiation experiments with the CRP materials. In addition to the irradiation and testing of.