Skip to main content

Irradiation Embrittlement Of Reactor Pressure Vessels Rpvs In Nuclear Power Plants

In Order to Read Online or Download Irradiation Embrittlement Of Reactor Pressure Vessels Rpvs In Nuclear Power Plants Full eBooks in PDF, EPUB, Tuebl and Mobi you need to create a Free account. Get any books you like and read everywhere you want. Fast Download Speed ~ Commercial & Ad Free. We cannot guarantee that every book is in the library!

Irradiation Embrittlement of Reactor Pressure Vessels RPVs in Nuclear Power Plants

Irradiation Embrittlement of Reactor Pressure Vessels  RPVs  in Nuclear Power Plants Book
Author : Naoki Soneda
Publisher : Elsevier
Release : 2014-09-01
ISBN : 0857096478
Language : En, Es, Fr & De

GET BOOK

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

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels Book
Author : Lendell E. Steele
Publisher : ASTM International
Release : 1993-01-01
ISBN : 9780803114784
Language : En, Es, Fr & De

GET BOOK

Book Description :

Download Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels book written by Lendell E. Steele, available in PDF, EPUB, and Kindle, or read full book online anywhere and anytime. Compatible with any devices.

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 Book
Author : International Atomic Energy Agency
Publisher : IAEA
Release : 2005
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

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.

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 Book
Author : International Atomic Energy Agency
Publisher : IAEA
Release : 2005
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

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.

Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels

Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels Book
Author : Lendell E. Steele
Publisher : ASTM International
Release : 1983
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

Download Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels book written by Lendell E. Steele, available in PDF, EPUB, and Kindle, or read full book online anywhere and anytime. Compatible with any devices.

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

Overview of the Activities in Spain on Irradiation Embrittlement of RPV Steel Book
Author : A. Ballesteros,J. Bros
Publisher : Unknown
Release : 1994
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

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.

Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region

Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region Book
Author : K. Sakamoto,S. Hatano,T. Osaki
Publisher : Unknown
Release : 2004
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

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.

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 Book
Author : International Atomic Energy Agency
Publisher : IAEA
Release : 2005
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

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.

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 Book
Author : International Atomic Energy Agency
Publisher : IAEA
Release : 2005
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

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.

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 Book
Author : AV. Nikolaeva,YA. Nikolaev
Publisher : Unknown
Release : 2000
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

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 Book
Author : IAEA.
Publisher : Unknown
Release : 2005
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

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.

Long Term Irradiation Phenomena in RPV Steels The LONGLIFE Project

Long Term Irradiation Phenomena in RPV Steels  The LONGLIFE Project Book
Author : Hieronymus Hein,Eberhard Altstadt,Frank Bergner
Publisher : Unknown
Release : 2013
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

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.

The LONGLIFE European Approach for Long Term Operation

The LONGLIFE European Approach for Long Term Operation Book
Author : Antonio Ballesteros Avila
Publisher : Unknown
Release : 2018
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

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.

Thermal Annealing of the Reactor Pressure Vessel NPP Unit 2 in Jaslovsk Bohunice for Its Radiation Embrittlement Regeneration

Thermal Annealing of the Reactor Pressure Vessel NPP Unit 2 in Jaslovsk   Bohunice for Its Radiation Embrittlement Regeneration Book
Author : Š Cepcek,L. Kupca
Publisher : Unknown
Release : 1993
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

The status of the preparation works tor the thermal annealing operation at reactor pressure vessel (RPV) V-230-type Unit 2 in Jaslovské Bohunice planned for Autumn 1993 is presented in this paper. The producer of the RPV W-213 type. ŠKODA Works, will perform the thermal annealing operation and manufacture all equipment needed. During the planned shutdown for the refueling operation of this unit in September 1989, samples were prepared from base material (BM) and weld metal (WM) by means of special equipment used for the analysis of the chemical composition in the Nuclear Power Plants Research Institute (VÚJE) laboratories. Results of the analysis of the irradiated samples and the hardness measurements of RPV material before and after annealing operation serve as the measure of radiation embrittlement recovery efficiency. Possible extension of the operation life of RPVs of WWER type by means of suitable provisions during normal operation before thermal annealing is also discussed.

Structural Alloys for Nuclear Energy Applications

Structural Alloys for Nuclear Energy Applications Book
Author : Robert Odette,Steven Zinkle
Publisher : Newnes
Release : 2019-08-15
ISBN : 012397349X
Language : En, Es, Fr & De

GET BOOK

Book Description :

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) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors’ unique personal insight from decades of frontline research, engineering and management. Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.

Understanding and Mitigating Ageing in Nuclear Power Plants

Understanding and Mitigating Ageing in Nuclear Power Plants Book
Author : Philip G Tipping
Publisher : Elsevier
Release : 2010-10-26
ISBN : 1845699955
Language : En, Es, Fr & De

GET BOOK

Book Description :

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

Microstructure Response of WWER 440 Reactor Pressure Vessel Weld Material After Irradiation and Annealing Treatment

Microstructure Response of WWER 440 Reactor Pressure Vessel Weld Material After Irradiation and Annealing Treatment Book
Author : A. Zeman,A. Ballesteros,A. Chernobaeva,L. Debarberis,D. Erak,V. Grafutin,A. Nikitin,S. Rogozhkin
Publisher : Unknown
Release : 2013
ISBN : 0987650XXX
Language : En, Es, Fr & De

GET BOOK

Book Description :

The aim of this publication is to contribute to the recent research and development efforts on mitigation of the reactor pressure vessel (RPV) embrittlement for operational lifetime extension. This research was done in the framework of the PRIMAVERA international project and it was focused on the WWER-440 reactor pressure vessel materials, specifically weld metals. The investigation primarily addressed the issues related to the re-irradiation effects and annealing treatment of "Russian-type" weld metals. A series of experimental data for WWER-440 reactor pressure vessel welds are reported and discussed to analyse the effect of the recovery annealing procedure. The specific annealing process has been developed and practically applied for "Russian-type" reactor pressure vessels to recover the negative effect of radiation embrittlement. Besides mechanical properties, more detailed information regarding microstructure evolution is described because it brings additional information which can help to understand the embrittlement-annealing-re-embrittlement processes. This study contributes to the experimental investigation of three different welds with high levels of copper (0.16 wt. %) and variable content of phosphorus (0.027-0.038 wt. %) at four different stages (unirradiated, irradiated, annealed after irradiation, and re-irradiated after annealing). The specimens were irradiated in the nuclear power plant (NPP) Rovno-1 and Rovno-2 up to a fluence of ~1.2 x 1023n/m2 and approximately 1.2 x 1024n/m2 and 5.9 x 1024n/m2 (En > 0.5 MeV) for the re-irradiation stage. After the first stage of irradiation, the samples were annealed in accordance with standard regime for WWER-440 RPVs (475°C, 100 h). The flux was about 4 x 1015n/m2s (Rovno-1) and 2 x 1016n/m2s (Rovno-2), respectively. The analysis of microstructure was done by atom probe tomography (APT) to obtain information concerning precipitation kinetics of Cu and P segregation, as well as interaction with other alloying elements. Further study of point-type defects and their clustering was analysed by positron annihilation spectroscopy techniques. The paper aims to report on behaviour of investigated RPV weld materials which were irradiated and annealed to analyse the response of main mechanical properties and microstructural parameters. The authors also believe that this study will be of value to the specialists and experts who are involved in the assessment of "Western-type" reactor pressure vessels, which is carried out as a part of ongoing international activities related to the safe and long term operation of present NPP fleet.

Comprehensive Nuclear Materials

Comprehensive Nuclear Materials Book
Author : Anonim
Publisher : Elsevier
Release : 2020-07-22
ISBN : 0081028660
Language : En, Es, Fr & De

GET BOOK

Book Description :

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), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials 2e provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field