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Book The Effects of Composition and Irradiation Conditions on the Post irradiation Annealing Kinetics of Pressure Vessel Steels

Download or read book The Effects of Composition and Irradiation Conditions on the Post irradiation Annealing Kinetics of Pressure Vessel Steels written by Erik V. Mader and published by . This book was released on 1991 with total page 152 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 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 Irradiation  Annealing  and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels

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.

Book Irradiation Embrittlement of LWR Pressure Vessel Steels

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 Structure and Composition Effects on Irradiation Sensitivity of Pressure Vessel Steels

Download or read book Structure and Composition Effects on Irradiation Sensitivity of Pressure Vessel Steels written by LE. Steele and published by . This book was released on 1970 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: The paper emphasizes engineering implications of the effects of structure and composition on the irradiation sensitivity of steels. Theoretical considerations are discussed and reviewed as they relate to possible explanations for observations on the subject.

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 Scientific and Technical Aerospace Reports

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1995 with total page 542 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Effect of Flux on the Irradiation Hardening of Pressure Vessel Steels

Download or read book The Effect of Flux on the Irradiation Hardening of Pressure Vessel Steels written by CA. English and published by . This book was released on 1994 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: Hardening of low copper steels irradiated at 288°C increased with increasing flux in the range from about 0.6 to 50 x 1016 n/m2-s. In contrast, the hardening of high copper steels was generally less effected and, in some cases, decreased with increasing flux. Thus there are at least two competing effects of flux. The behavior of low copper alloys is attributed to a population of thermally unstable matrix defects that anneal during irradiation, hence, produce hardening that increases with flux. However, the unstable matrix defects also act as point defect sinks reducing radiation enhanced solute diffusion rates. In high copper steels, lower diffusion rates delay hardening due to precipitation. These conclusions were confirmed by low-temperature post-irradiation annealing treatments which produced rapid recovery of the unstable matrix defects. The observed data trends are consistent with a model that treats the unstable matrix defects as small cascade vacancy clusters.

Book Irradiation Response and Annealing Behavior of Pressure Vessel Model Steels and Iron Ternary Alloys Measured with Positron Techniques

Download or read book Irradiation Response and Annealing Behavior of Pressure Vessel Model Steels and Iron Ternary Alloys Measured with Positron Techniques written by P. Hautojarvi and published by . This book was released on 1992 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: Positron lifetime and annihilation gamma-line Doppler broadening measurements were used to study the irradiation response and postirradiation annealing behavior of pressure vessel model steels and ternary iron alloys. The steel samples had the basic composition of A533-B and A302-B type steels with varying key impurity elements, i.e., Cu, P, and Ni. The steels and the ternary iron alloys were neutron irradiated at 288°C into a fluence of 2.5 and 4.6 ? 1023 neutrons/m-2, E > 1 MeV, respectively.

Book Investigation of the Development of Irradiation   Induced Precipitates in VVER 440 Type Reactor Pressure Vessel Steels and Weld Metals After Irradiation and Annealing

Download or read book Investigation of the Development of Irradiation Induced Precipitates in VVER 440 Type Reactor Pressure Vessel Steels and Weld Metals After Irradiation and Annealing written by J. Böhmert and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The development of irradiation-induced precipitates in VVER-440 type reactor pressure vessel steels 15Kh2MFA and weld metals SV-10KhMFT during irradiation and post-irradiation annealing is studied by small angle neutron and X-ray scattering. The kinetic conditions for the precipitation of particles, which already exist in the unirradiated state, seem to be improved at temperatures of about 270°C due to the irradiation. The size distribution of the irradiation-induced precipitates depends on the copper content and differs between weld and base metal. A strong correlation between the formation of irradiation-induced precipitates and the irradiation hardening is found. The hardness nearly linearly depends on the number of these precipitates.

Book The Influence of Neutron Exposure  Chemical Composition and Metallurgical Condition  on the Irradiation Shift of Reactor Pressure Vessel Steels

Download or read book The Influence of Neutron Exposure Chemical Composition and Metallurgical Condition on the Irradiation Shift of Reactor Pressure Vessel Steels written by M. Austin and published by . This book was released on 1982 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: The work described in this paper is part of a continuing programme to produce well-characterized data for use in the development of models for the prediction of irradiation shift in pressurized water reactor steels. Results are presented for around 50 batches of Charpy specimens, irradiated either in the DIDO or PLUTO heavy water, or in the HERALD light water, research reactors, to doses up to 35 mdpa (?2 x 1019 n/cm2, E > 1MeV). The materials include A533B plate, weld, and heat affected zones. The results are compatible with a log/log relationship between dose and shift with an exponent of 0.5 for all materials. They also show that irradiation response is dependent on heat treatment condition. If it is assumed that the Varsik and Byrne Chemistry Relationship, or a similar expression, is an appropriate parameter to characterize the effect of chemical composition on irradiation sensitivity, the results also demonstrate a difference between plate and weld irradiation sensitivity. An empirical model of the data has been developed and assessed, and this is compared with the Odette physically-based irradiation damage model.

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 Thermodynamic and Kinetic Modeling of Evolution of Mn Ni Si rich Precipitates in Low Cu Reactor Pressure Vessel Steels

Download or read book Thermodynamic and Kinetic Modeling of Evolution of Mn Ni Si rich Precipitates in Low Cu Reactor Pressure Vessel Steels written by Huibin Ke and published by . This book was released on 2017 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Formation of large volume fractions of Mn-Ni-Si precipitates (MNSPs) causes excess irradiation embrittlement of reactor pressure vessel (RPV) steels at high, extended-life fluences. Thus, a new and unique, semi-empirical cluster dynamics model was developed to study the evolution of MNSPs in low-Cu RPV steels. The model has been developed based on experimental data under irradiation conditions and validated against data on post-irradiation annealing conditions. The model is based on CALPHAD thermodynamics and radiation enhanced diffusion kinetics. The thermodynamics dictates the compositional and temperature dependence of the free energy reductions that drive precipitation. The model treats both homogeneous and heterogeneous nucleation, where the latter occurs on cascade damage, like dislocation loops. The model has only four adjustable parameters that were fit to an atom probe tomography (APT) database. The model predictions are in semi-quantitative agreement with systematic Mn, Ni and Si composition variations in the alloys characterized by APT, including a sensitivity to local tip-to-tip variations even in the same steel. The model predicts that heterogeneous nucleation plays a critical role in MNSP formation in lower alloy Ni contents. Single variable assessments of compositional effects show that Ni plays a dominant role, while even small variations in irradiation temperature can have a large effect on the MNSP evolution. Within typical RPV steel ranges, Mn and Si have smaller effects. The delayed but then rapid growth of MNSPs to large volume fractions at high fluence is well predicted by the model. For purposes of illustration, rather than prediction, the effect of MNSPs on transition temperature shifts are presented based on well-established microstructure-property and property-property models. Solubility of Fe in MNSPs is also investigated with ab initio method and is found that the solubility of Fe is less than 1.0% in G-phase formed in typical RPV steels.