Download or read book Influence of Thermal Neutrons on the Hardening and Embrittlement of Plate Steels written by MR. Wootton and published by . This book was released on 2000 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of C-Mn pressure vessel plates and other steels containing various levels of copper, phosphorus and boron were irradiated at 240°C in two differing neutron spectra in the Halden reactor. Hardening and embrittlement data obtained after exposure in a highly thermalised neutron spectrum with dpathermal(>1keV)/dpafast(

Download or read book The Dependence of Radiation Hardening and Embrittlement on Irradiation Temperature written by RB. Jones and published by . This book was released on 1996 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: Assessments of the hardening and embrittlement of pressure vessel steels and welds as a function of neutron dose use trend curves derived from surveillance programmes and accelerated irradiation data. A temperature dependent factor is incorporated for assessing vessel locations operating at different temperatures. As hardening and embrittlement arise from the sum of matrix damage and copper impurity precipitation, the influence of irradiation temperature on each process needs to be established. For irradiations performed below ~300°C recent data shows that the dose-dependent growth of copper precipitates ceases at a mean diameter of about 2 nm that also corresponds to peak hardening and embrittlement by copper. For doses beyond this peak copper dose the property-dependence on irradiation temperature can be identified with that of matrix damage alone. An analysis of several experiments on plate steels, performed at differing irradiation temperatures, has permitted the temperature dependence of matrix hardening to be defined by the simple empirical factor FT=1.869-4.57x10-3T where T is the irradiation temperature. When a linear correlation between irradiation hardening and embrittlement is observed, then FT can be used to analyse the temperature dependence of matrix embrittlement. The validity of using FT in successfully correlating irradiation results has been demonstrated for several plate steels and welds with differing copper contents.

Download or read book Effect of Neutron Bombardment Upon the Properties of ASTM Type SA212B Steel written by Melvin L. Bleiberg and published by . This book was released on 1955 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Effects on Structural Alloys for Nuclear Reactor Applications written by A. L. Bement and published by ASTM International. This book was released on 1971 with total page 571 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by Margaret L. Hamilton and published by ASTM International. This book was released on 2000 with total page 1266 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Influence of Phosphorus on Thermal and Neutron Embrittlement of Pressure Vessel Steels written by H. Horowitz and published by . This book was released on 1993 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: In conjunction with an international study coordinated by the International Atomic Energy Agency (IAEA), a review was made of three Japanese model steels with different phosphorus and copper contents irradiated at 5.1019 n • cm-2 (E > 1 MeV) to explain the influence of phosphorus on the thermal and neutron embrittlement of steels.

Download or read book Irradiation Hardening of Pressure Vessel Steels at 60 C written by D. Klingensmith and published by . This book was released on 1999 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Six split melt A533B-type model alloys, with different combinations of copper, nickel and boron contents, were irradiated at 60°C in a neutron spectrum with a thermal-to-fast (E > 1 MeV) ratio of about 370. The resulting yield stress increases were compared to hardening produced by irradiations at a low thermal-to-fast flux ratio. The latter data were obtained in a larger experiment on 60°C hardening that showed: i) a negligible effect of flux; ii) hardening increases with the square root of fluence above a low threshold; and iii) an individually weak, but collectively significant, influence of copper, nickel, manganese, phosphorous and molybdenum. These and other observations have been interpreted to suggest that low temperature hardening is caused by features formed in displacement cascades. However, this interpretation is not consistent with the results of this study which show that yield stress increases are even larger for conditions dominated by low energy PKAs created by thermal neutrons. The thermal-to-fast dpa hardening efficiency factor was estimated to be about 1.7±0.5, which is comparable to the corresponding theoretical ratio of residual defects. The data also suggest that transmutant products from the 10B(n,?) reaction may contribute a small increment to hardening.

Download or read book Effect of Neutron Irradiation on Mechanical Properties of Ferritic Steels written by and published by . This book was released on 1995 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Effect of neutron radiation exposure was investigated in various ferritic steels with the main emphasis being the effects of thermal neutrons on radiation hardening. Pure iron of varied grain sizes was also used for characterizing the grain size effects on the source hardening before and after neutron irradiation. While many steels are considered in the overall study, the results on 1020, A516 and A588 steels are emphasized. Radiation hardening due to fast neutrons was seen to be sensitive to the composition of the steels with A354 being the least resistant and A490 the least sensitive. Majority of the radiation hardening stems from friction hardening, and source hardening term decreased with exposure to neutron radiation apparently due to the interaction of interstitial impurities with radiation produced defects. Inclusion of thermal neutrons along with fast resulted in further decrease in the source hardening with a slight increase in the friction hardening which revealed a critical grain size below which exposure to total (fast and thermal) neutron spectrum resulted in a slight reduction in the yield stress compared to the exposure to only fast neutrons. This is the first time such a grain size effect is reported and this is shown to be consistent with known radiation effects on friction and source hardening terms along with the observation that low energy neutrons have a nonnegligible effect on the mechanical properties of steels. In ferritic steels, however, despite their small grain size, exposure to total neutron spectrum yielded higher strengths than exposure to only fast neutrons. This behavior is consistent with the fact that the source hardening is small in these alloys and radiation effect is due only to friction stress.

Download or read book The Effects of Neutron Spectrum and Dose Rate on Radiation Hardening and Embrittlement in Steels written by D.R. Harries and published by . This book was released on 1962 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Effects of Microstructure and Thermal Aging on Neutron Irradiation Embrittlement of 21 4Cr 1Mo Steel for a Nuclear Pressure Vessel written by M. Suzuki and published by . This book was released on 1987 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Plate, weld, and heat-affected zone (HAZ) materials of 21⁄4Cr-1Mo steels, designated as ASTM A387 Grade 22 Cl.1, and Cl.2 were irradiated at around 400°C to a fluence of about 2 x 1018 n/cm2 (E > 1 MeV). A387 Grade 22 Cl.2 with bainite has a lower susceptibility to neutron irradiation embrittlement than A387 Grade 22 Cl.1 with ferrite plus bainite. The anomalous ductile to brittle transition behavior of A387 Grade 22 Cl.2 was explained by taking into account the parameter ky, which is a constant in the Cottrell-Petch equation. It is concluded that there does not exist any strong interaction between thermal aging embrittlement and neutron irradiation embrittlement.

Download or read book Structural Alloys for Nuclear Energy Applications written by Robert Odette and published by Newnes. This book was released on 2019-08-15 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

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:

Download or read book The effects of composition and heat treatment on hardening and embrittlement of reactor pressure vessel steels written by G. R. Odette and published by . This book was released on 2002 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Irradiation in Austenitic Steels and Other High Temperature Alloys written by D. R. Harries and published by . This book was released on 1965 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron irradiation has an adverse effect on the tensile ductility of austenitic steels and a nickel-base alloy at test temperatures above about 600 C. n contrast to the fast-neutron-induced, low-temperature irradiation hardening and embrittlement of materials, the loss in ductility at elevated temperatures is a function of the thermal neutron dose, and the effects cannot be recovered by post-irradiation annealing at temperatures up to about 1200 C.

Download or read book The Effects of Neutron Spectrum and Dose Rate on Radiation Hardening and Embrittlement in Steels written by and published by . This book was released on 1962 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by and published by . This book was released on 2000 with total page 1296 pages. Available in PDF, EPUB and Kindle. Book excerpt: