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On The Mechanism Of Irradiation Embrittlement Enhancement In Reactor Pressure Vessel Steels At High Neutron Fluences
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Book Synopsis On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences by : IA. Stepanov
Download or read book On the Mechanism of Irradiation Embrittlement Enhancement in Reactor Pressure Vessel Steels at High Neutron Fluences written by IA. Stepanov and published by . This book was released on 2004 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The DBTT shift in irradiated VVER pressure vessel steels is represented by standard guidelines with a power law dependence on fast neutron fluence multiplied by a material constant. However, from recent data on surveillance specimens for several units of VVER-440, an irradiation embrittlement enhancement has been observed at neutron fluences above (2-3)x1020 n/cm2 (E>0.5 MeV) with a significant deviation from the standard guideline. This suggests an additional mechanism of irradiation embrittlement at high fluences.
Book Synopsis Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels by : Lendell E. Steele
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 Synopsis Effects of Nickel on Irradiation Embrittlement of Light Water Reactor Pressure Vessel Steels by : International Atomic Energy Agency
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.
Book Synopsis Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels by : Lendell E. Steele
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 Synopsis Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels by : Lendell E. Steele
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 Synopsis Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels by : Lendell E. Steele
Download or read book Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels written by Lendell E. Steele and published by . This book was released on 1975 with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels by : Lendell E. Steele
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 Synopsis Apparent Embrittlement Saturation and Radiation Mechanisms of Reactor Pressure Vessel Steels by : D. Pachur
Download or read book Apparent Embrittlement Saturation and Radiation Mechanisms of Reactor Pressure Vessel Steels written by D. Pachur and published by . This book was released on 1981 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The irradiation and annealing results of three different reactor pressure vessel steels are reported. Steel A, a basic material according to ASTM A 533-B, was produced by Lukens as HSST Plate 03; Steel B was a modified A 533 B having 0.15 percent vanadium; and Steel C contained 3.2 percent nickel. The steels were irradiated at 150, 300, and 400°C with neutron fluxes of 6 x 1011 and 3 x 1013 neutrons (n)/cm2s [E > 1 MeV] to different neutron fluences in the research reactors Forschungs-Reactor Jülich (FRJ)-1 and FRJ-2 in Jülich, Germany.
Book Synopsis Irradiation Embrittlement of Reactor Pressure Vessel Steels by : GE. Lucas
Download or read book Irradiation Embrittlement of Reactor Pressure Vessel Steels written by GE. Lucas and published by . This book was released on 1986 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: A model of irradiation embrittlement is described for predicting the 41-J Charpy V-notch temperature shifts (?T) as a function of metallurgical variables and neutron exposure conditions. This forecasting procedure combines semi-empirical physical models with statistical analyses of test and power reactor data, and calibration against data from fundamental experiments in which both mechanical property and microstructural changes are evaluated. The models are based on the evolution of a damage microstructure, which includes both copper precipitates and a radiation damage component enhanced by nickel. The precipitate volume is also increased by nickel and impurity phosphorus. Predicted hardening and shifts associated with these extended defects are based on empirically validated models. The model is able to self-consistently rationalize a wide array of microstructural and mechanical property data for commercial pressure vessel steels as well as model alloys.
Book Synopsis Effects of Radiation on Materials by : Martin L. Grossbeck
Download or read book Effects of Radiation on Materials written by Martin L. Grossbeck and published by ASTM International. This book was released on 2004 with total page 767 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Survey of postirradiation heat treatment as a means to mitigate radiation embrittlement of reactor vessel steels by : J. R. Hawthorne
Download or read book Survey of postirradiation heat treatment as a means to mitigate radiation embrittlement of reactor vessel steels written by J. R. Hawthorne and published by . This book was released on 1979 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel by : PN. Randall
Download or read book Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel written by PN. Randall and published by . This book was released on 1989 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper is in several parts: the first presents an overview of research activities sponsored by the U.S. Nuclear Regulatory Commission (NRC) on neutron irradiation embrittlement of pressure vessel steels. A series of irradiation experiments have evaluated effects of chemistry on the fracture toughness properties of submerged arc welds representing current nuclear vessel fabrication practices and provide data to validate ASME Code practices. A correlation between Charpy energy and fracture toughness is being studied as is a program on radiation sensitivity to define the role of dose rate and to study the effects of postirradiation heat treatment (annealing). The development of a comprehensive data base for radiation embrittlement data has been initiated and is being applied in a correlation of reactor surveillance data with test reactor data. A comprehensive dosimetry effort has produced validated standard methods for calculating and measuring neutron flux and fluence parameters and the correlation of these parameters to embrittlement of pressure vessel steels in light water reactors. Our knowledge of radiation damage to reactor vessels has also been greatly increased in recent years by the accumulation of power reactor surveillance data and by better models and better analysis techniques applied to that data. Unfortunately, the results show that radiation damage is often more than previously predicted, using Revision 1 of NRC Regulatory Guide 1.99, and will result in more restrictive pressure temperature limits. The second part of this paper describes some of the system and operational impacts produced, which in turn lead to challenges to long-established safety margins. Finally, a number of outstanding issues which require further research are discussed, many of which will require better understanding of radiation damage mechanisms.
Book Synopsis The Effect of Neutron Flux on Radiation-Induced Embrittlement in Reactor Pressure Vessel Steels by : RE. Stoller
Download or read book The Effect of Neutron Flux on Radiation-Induced Embrittlement in Reactor Pressure Vessel Steels written by RE. Stoller and published by . This book was released on 2004 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effect of neutron flux level is a longstanding concern for determining the applicability of test reactor data or high lead-factor surveillance data to the prediction of embrittlement in commercial reactor pressure vessels (RPV). However, as operating reactors reach higher fluences, the question of flux effects is becoming increasingly relevant for situations such as embrittlement attenuation through the (RPV) and the comparison of boiling and pressurized reactor RPVs. In spite of its technological importance and extensive experimental and theoretical investigation, the issue of neutron flux effects on radiation-induced embrittlement in RPV steels remains unresolved. For neutron fluxes much greater than RPV operating conditions (>100 times higher), a regime exists in which the effects of flux are well defined experimentally and are well predicted by current models. These same models predict that the effect of flux should be relatively weak for values near those obtained in commercial RPVs, but may increase at lower fluxes. However, it is difficult to obtain sufficient data at low to intermediate fluxes to unambiguously determine the effects of flux since the time required to reach the desired fluences is necessarily long. In order to demonstrate the potential effects of flux on RPV embrittlement, and to help interpret the available experiments, a kinetic embrittlement model has been used in an analysis of the primary variables involved. The results of the analysis are consistent with a modest effect of flux on embrittlement for fluxes near those typical of commercial RPVs.
Book Synopsis Effects Of Irradiation Temperature on Embrittlement of Nuclear Pressure Vessel Steels by : FM. Haggag
Download or read book Effects Of Irradiation Temperature on Embrittlement of Nuclear Pressure Vessel Steels written by FM. Haggag and published by . This book was released on 1994 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-cooled reactor (MHTGR) are eing investigated, primarily because the operating temperatures are low [121 to 288°C (250-550°F)] compared to those for commercial light-water reactors (LWRs) [~288°C (550°F)]. The need for design data on the reference temperature (RTNDT) shift necessitated the irradiation at different temperatures of A 533 grade B class 1 plates, A 508 class 3 forging, and welds used for the vessel shell, vessel closure head, and vessel flange. This paper presents regular- and mini-tensile, Automated Ball Indentation (ABI), and Charpy V-notch (CVN) impact test results from five irradiation capsules of this program. The first four capsules were irradiated in the University of Buffalo Reactor (UBR) to an effective fast fluence of 1.1 x 1018 neutrons/cm2 [0.7 x 1018 neutrons/cm2 (>1 MeV)] at temperatures of 288, 204, 163, and 121°C (550, 400, 325, and 250°F), respectively. The fifth capsule (designated ORNL-7) was irradiated in the Ford Nuclear Reactor (FNR) of the University of Michigan at 60°C (140°F) to an effective fast fluence of 1.3 x 1018 neutrons/cm2 [0.8 x 1018 neutrons/cm2 (>1 MeV)]. The yield and ultimate strengths of both A 533 grade B class 1 plate materials of the MHTGR program increased with decreasing irradiation temperature. Similarly, the 41-J CVN transition temperature shift increased with decreasing irradiation temperature (in agreement with the increase in yield strength). The mini-tensile and Automated Ball Indentation (ABI) test results (yield strength and flow properties) were in good agreement with those from standard tensile specimens. The mini-tensile and ABI test results were also used in a model which utilizes the changes in yield strength to estimate the CVN ductile-to-brittle transition temperature shift due to irradiation. The model predictions were compared with CVN test results obtained here and in earlier work.
Book Synopsis Structural Characterization of Nanoscale Intermetallic Precipitates in Highly Neutron Irradiated Reactor Pressure Vessel Steels by :
Download or read book Structural Characterization of Nanoscale Intermetallic Precipitates in Highly Neutron Irradiated Reactor Pressure Vessel Steels written by and published by . This book was released on 2015 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Here, massive, thick-walled pressure vessels are permanent nuclear reactor structures that are exposed to a damaging flux of neutrons from the adjacent core. The neutrons cause embrittlement of the vessel steel that increases with dose (fluence or service time), as manifested by an increasing temperature transition from ductile-to-brittle fracture. Moreover, extending reactor life requires demonstrating that large safety margins against brittle fracture are maintained at the higher neutron fluence associated with 60 to 80 years of service. Here synchrotron-based x-ray diffraction and small angle x-ray scattering measurements are used to characterize a new class of highly embrittling nm-scale Mn-Ni-Si precipitates that develop in the irradiated steels at high fluence. Furthermore, these precipitates can lead to severe embrittlement that is not accounted for in current regulatory models. Application of the complementarity techniques has, for the very first time, successfully characterized the crystal structures of the nanoprecipitates, while also yielding self-consistent compositions, volume fractions and size distributions.
Book Synopsis Irradiation Embrittlement of LWR Pressure Vessel Steels by : G. R. Odette
Download or read book Irradiation Embrittlement of LWR Pressure Vessel Steels written by G. R. Odette and published by . This book was released on 1989 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron Irradiation Embrittlement of Several Higher Strength Steels by : Lendell E. Steele
Download or read book Neutron Irradiation Embrittlement of Several Higher Strength Steels written by Lendell E. Steele and published by . This book was released on 1966 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: Several steels representative of recently developed types and having potential for nuclear structural applications were exposed to high energy nuclear radiation, and the resultant properties were compared with those of the currently used A212-B and A302-B nuclear reactor pressure vessel steels. Preliminary results from several comparative irradiation experiments indicate that certain higher strength steels, in addition to having initial qualities of higher strength and lower initial ductile-brittle transition temperatures, show smaller embrittlement, earlier embrittlement saturation, and a superior overall response to irradiation at 550F than that observed for the steels in current reactor pressure vessels. (Author).
