Download or read book Irradiation Embrittlement of Reactor Pressure Vessels RPVs in Nuclear Power Plants written by Naoki Soneda and published by Elsevier. This book was released on 2014-09-01 with total page 437 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Download or read book Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels written by Lendell E. Steele and published by ASTM International. This book was released on 1983 with total page 240 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Integrity of Reactor Pressure Vessels in Nuclear Power Plants written by and published by . This book was released on 2009 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is intended to assist nuclear utilities in optimizing 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.
Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels written by Lendell E. Steele and published by ASTM International. This book was released on 1989 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels written by Lendell E. Steele and published by ASTM International. This book was released on 1986 with total page 303 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Impact of U S NRC Reactor Vessel Embrittlement Research on Regulation of Nuclear Power Plants written by CZ. Serpan and published by . This book was released on 1994 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: The embrittlement of nuclear reactor pressure vessels caused by neutron radiation is the chief aging mechanism of these critical components. It is so critical to safe operation of reactors that the U.S. Nuclear Regulatory Commission (USNRC) and its predecessor, the Atomic Energy Commission, have spent millions of dollars over the past three decades to document the effects. Furthermore, USNRC regulations and associated regulatory documents derived from that research basis now provide guidance on establishing operational conditions to assure that the pressure vessels of U.S. reactors will behave in a ductile manner, and that vessel materials will exhibit a sufficiently high resistance to ductile fracture.
Download or read book Overview of the Activities in Spain on Irradiation Embrittlement of RPV Steel written by A. Ballesteros and published by . This book was released on 1994 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Irradiation Annealing and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels written by MA. Sokolov and published by . This book was released on 2000 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPVs) is to thermally anneal them to restore the toughness properties that have been degraded by neutron irradiation. Even though a postirradiation anneal may be deemed successful, a critical aspect of continued RPV operation is the rate of embrittlement upon reirradiation. There are insufficient data available to allow for verification of available models of reirradiation embrittlement or for the development of a reliable predictive methodology. This is especially true in the case of fracture toughness data. Under the U.S.-Russia Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS), Working Group 3 on Radiation Embrittlement, Structural Integrity, and Life Extension of Reactor Vessels and Supports agreed to conduct a comparative study of annealing and reirradiation effects on RPV steels. The Working Group agreed that each side would irradiate, anneal, reirradiate (if feasible), and test two materials of the other. Charpy V-notch (CVN) and tensile specimens were included. Oak Ridge National Laboratory (ORNL) conducted such a program (irradiation and annealing, including static fracture toughness) with two weld metals representative of VVER-440 and VVER-1000 RPVs, while the Russian Research Center-Kurchatov Institute (RRC-KI) conducted a program (irradiation, annealing, reirradiation, and reannealing) with Heavy-Section Steel Technology (HSST) Program Plate 02 and Heavy-Section Steel Irradiation (HSSI) Program Weld 73W. The results for each material from each laboratory are compared with those from the other laboratory. The ORNL experiments with the VVER welds included irradiation to about 1 x 1019 n/cm2 (>1 MeV), while the RRC-KI experiments with the U.S. materials included irradiations from about 2 to 18 x 1019 n/cm2 (>1 MeV). In both cases, irradiations were conducted at ~290 °C and annealing treatments were conducted at ~454 °C. The ORNL and RRC-KI experiments have shown generally good agreement for both the Russian and U.S. steels. While recoveries of the Charpy 41-J transition temperatures were substantial in all cases, significantly less recovery of the lateral expansion and shear fracture in some cases (no recovery in one case) deserves further attention. The RRC-KI results for the U.S. steels showed reirradiation embrittlement rates which are conservative relative to the lateral shift prediction based on Charpy impact energy.
Download or read book Neutron Irradiation Embrittlement of Pressure Vessel Materials in Spanish Nuclear Power Reactors written by A. Ballesteros and published by . This book was released on 1992 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: The exposure of reactor vessel materials to a fast neutron flux causes a number of mechanical property changes. For instance, the brittle-to-ductile transition temperature increases and the fracture toughness is reduced. Pressure water reactors and boiling water reactors contain a series of pressure vessel steel surveillance capsules as the principal means of monitoring radiation effects on the pressure vessel.
Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels 3 written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Radiation embrittlement of nuclear reactor pressure vessel steels written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Development of RPV Embrittlement Evaluation Technology for Charpy Upper Shelf Region written by K. Sakamoto and published by . This book was released on 2004 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Guidelines for Prediction of Irradiation Embrittlement of Operating WWER 440 Reactor Pressure Vessels written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Radiation Damage Exposure and Embrittlement of Reactor Pressure Vessels written by K. Shure and published by . This book was released on 1964 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity in Nuclear Power Plants written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
