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Book Evolution of the Microstructure of PWR Pressure Vessel Steels from the CHOOZ A Reactor Surveillance Program After Long Term Irradiations

Download or read book Evolution of the Microstructure of PWR Pressure Vessel Steels from the CHOOZ A Reactor Surveillance Program After Long Term Irradiations written by J. Bourgoin and published by . This book was released on 1992 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: We have studied the microstructural evolution of a pressure vessel steel (C shell base metal) irradiated in CHOOZ A reactor surveillance capsules. This material has been irradiated at 265°C with fluences ranging from 2.2 x 1019 to 14 x 1019 n • cm-2 (E > 1 MeV); the longest irradiation has lasted about 13 years. The maximum ?RTNDT measured is 145°C for a fluence of 9 x 1019 n • cm-2 (E > 1 MeV). The microstructural studies have been carried out by transmission electron microscopy (TEM) and small angle neutron scattering (SANS).

Book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

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 1993 with total page 405 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Roger E. Stoller and published by ASTM International. This book was released on 1992 with total page 1315 pages. Available in PDF, EPUB and Kindle. Book excerpt: Symposium held in Nashville, Tennessee, June 1990. Almost two-thirds of these 91 papers are authored by researchers outside of the US (including information on research in the former USSR, Japan, and Europe). Topics include: current commercial power reactor systems; microstructural characterization

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by D. S. Gelles and published by ASTM International. This book was released on 1996 with total page 1169 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by R. K. Nanstad and published by ASTM International. This book was released on 1999 with total page 1135 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

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:

Book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

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:

Book Metals Abstracts

Download or read book Metals Abstracts written by and published by . This book was released on 1993 with total page 606 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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

Download or read book Long Term Irradiation Effects on the Mechanical Properties of Reactor Pressure Vessel Steels from Two Commercial PWR Plants written by Jenny Rouden and published by . This book was released on 2013 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by and published by . This book was released on 1996 with total page 1192 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Meso structure in Materials

Download or read book Meso structure in Materials written by Omourtague Dimitrov and published by . This book was released on 1997 with total page 202 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Microstructure of the Neutron Irradiated VVER type Reactor Pressure Vessel Steels

Download or read book Microstructure of the Neutron Irradiated VVER type Reactor Pressure Vessel Steels written by I. Procházka and published by . This book was released on 2000 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Conventional transmission electron microscopy has been used to investigate the radiation-induced changes in the microstructure of VVER-type RPV steels. Specimens irradiated at ? 270 °C temperature in both the power light-water reactor (surveillance specimens) and the research reactor have been studied. In addition, the microstructure of the thermally aged specimens was analyzed too. Microstructural analysis has been supplemented by some preliminary results of the Doppler broadening and lifetime positron annihilation measurements.

Book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels

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 320 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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

Download or read book Microstructure Response of WWER 440 Reactor Pressure Vessel Weld Material After Irradiation and Annealing Treatment written by A. Zeman and published by . This book was released on 2013 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Radiation Damage of Nuclear Power Plant Pressure Vessel Steels

Download or read book Radiation Damage of Nuclear Power Plant Pressure Vessel Steels written by Nikolaĭ Nikolaevich Alekseenko and published by . This book was released on 1997 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes the current state of knowledge about pressure vessel material selection, fabrication (including welding), the changes in properties in service, and response to high-temperature annealing. In contrast to the bad reports of inadequate attention to reactor safety in the former Soviet Union, this book shows that the question of pressure vessel performance has received proper attention and a strong scientific base underlies the assessment of vessel life. This book should be read by reactor designers and operators and their scientific colleagues throughout the world.

Book Alloys Index

    Book Details:
  • Author :
  • Publisher :
  • Release : 1993
  • ISBN :
  • Pages : 950 pages

Download or read book Alloys Index written by and published by . This book was released on 1993 with total page 950 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation

Download or read book Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation written by International Atomic Energy Agency and published by . This book was released on 1986 with total page 119 pages. Available in PDF, EPUB and Kindle. Book excerpt: