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Mechanical Properties And Fracture Behavior Of 20 Cold Worked 316 Stainless Steel Irradiated To Very High Neutron Exposures
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Book Synopsis Mechanical Properties and Fracture Behavior of 20% Cold-Worked 316 Stainless Steel Irradiated to Very High Neutron Exposures by : FA. Garner
Download or read book Mechanical Properties and Fracture Behavior of 20% Cold-Worked 316 Stainless Steel Irradiated to Very High Neutron Exposures written by FA. Garner and published by . This book was released on 1987 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt: Stainless steels irradiated in EBR-II at temperatures in the range 380 to 500°C tend to exhibit saturation of mechanical properties at relatively low fluence levels. At fluences on the order of 13 to 15 x 1022 n/cm2 (E > 0.1 MeV), however, there is a rapid increase in hardness just after the onset of void swelling. The hardness increase is not attributed just to the voids themselves but rather to an indirect effect of voids on nickel depletion in the alloy matrix. The strong dependence of stacking fault energy on nickel and chromium content and particularly on deformation temperature combine to promote extensive stress-induced formation of ?-martensite at room temperature. This leads to a very brittle failure mode characterized as quasi-cleavage. At higher deformation temperatures it leads to a failure mode designated as channel fracture.
Book Synopsis Properties of 20% Cold-worked 316 Stainless Steel Irradiated at Low Dose Rate by :
Download or read book Properties of 20% Cold-worked 316 Stainless Steel Irradiated at Low Dose Rate written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: To assess the effects of long-term, low-dose-rate neutron exposure, tensile, hardness, and fracture properties were measured and microstructural characterization performed on irradiated 20% cold-worked Type 316 stainless steel. Samples were prepared from reactor core components retrieved from the EBR-II reactor following final shutdown. Sample locations were chosen to cover a dose range of 1-56 dpa at temperatures from 371-390 C and dose rates from 0.8-3.3 x 10−7 dpa/s. Irradiation caused hardening, with the ultimate tensile strength (UTS) reaching about 800 MPa near 20 dpa and appearing to saturate at higher doses. The yield strength (YS) follows approximately the same trend as the ultimate tensile strength. At higher dose, the difference between the UTS and YS decreases, suggesting the work-hardening capability of the material is decreasing with increasing dose. The hardness and yield strength increases occur roughly over the same range of dose. While the material retained respectable ductility at 20 dpa, the uniform and total elongation decreased to
Book Synopsis The Combined Effects of Temperature and Irradiation on the Mechanical Properties of Austenitic Stainless Steels by : J. E. Irvin
Download or read book The Combined Effects of Temperature and Irradiation on the Mechanical Properties of Austenitic Stainless Steels written by J. E. Irvin and published by . This book was released on 1965 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Properties of 20 % Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate by : H. Tsai
Download or read book Properties of 20 % Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate written by H. Tsai and published by . This book was released on 2004 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: To assess the effects of long-term, low-dose-rate neutron exposure, tensile, hardness, and fracture properties were measured, and microstructural characterization was performed on irradiated 20% cold-worked Type 316 stainless steel. Samples were prepared from reactor core components retrieved from the EBR-II reactor following final shutdown. Sample locations were chosen to cover a dose range of 1-56 dpa at temperatures from 371-390°C and dose rates from 0.8-3.3 × 10−7 dpa/s. Irradiation caused hardening, with the ultimate tensile strength (UTS) reaching about 800 MPa near 20 dpa and appearing to saturate at higher doses. The yield strength (YS) follows approximately the same trend as the ultimate tensile strength. The work-hardening capability of the material decreases with increasing dose. While the material retained respectable ductility at 20 dpa, the uniform and total elongation decreased to
Book Synopsis Influence of Radiation on Material Properties by : F. A. Garner
Download or read book Influence of Radiation on Material Properties written by F. A. Garner and published by ASTM International. This book was released on 1987 with total page 806 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1988 with total page 500 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis MECHANICAL PROPERTIES AND FRACTURE BEHAVIOUR OF 20 PERCENT COLD-WORKED 316 SS IRRADIATED TO VERY HIGH EXPOSURES. by : M. L. Hamilton
Download or read book MECHANICAL PROPERTIES AND FRACTURE BEHAVIOUR OF 20 PERCENT COLD-WORKED 316 SS IRRADIATED TO VERY HIGH EXPOSURES. written by M. L. Hamilton and published by . This book was released on 1991 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Mechanical Properties of 20% Cold-worked 316 Stainless Steel Irradiated at Low Dose Rate by :
Download or read book Mechanical Properties of 20% Cold-worked 316 Stainless Steel Irradiated at Low Dose Rate written by and published by . This book was released on 2001 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: To assess the effects of long-term, low-dose-rate neutron exposure on mechanical strength and ductility, tensile properties were measured on irradiated 20% cold-worked Type 316 stainless steel. Samples were prepared from reactor core components retrieved from the EBR-II reactor following final shutdown. Sample locations were chosen to cover a dose range of 1-47 dpa at temperatures from 371-385 C and dose rates from 0.8-2.8 x 10−7 dpa/s. These dose rates are about one order of magnitude lower than those of typical EBR-II in-core experiments. Irradiation caused hardening, with the yield strength (YS) following approximately the same trend as the ultimate tensile strength (UTS). At higher dose, the difference between the UTS and YS decreases, suggesting the work-hardening capability of the material is decreasing with increasing dose. Both the uniform elongation and total elongation decrease up to the largest dose. Unlike the strength data, the ductility reduction showed no signs of saturated at 20 dpa. While the material retained respectable ductility at 20 dpa, the uniform and total elongation decreased to
Book Synopsis Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors by : John H. Jackson
Download or read book Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors written by John H. Jackson and published by Springer. This book was released on 2018-12-20 with total page 2532 pages. Available in PDF, EPUB and Kindle. Book excerpt: This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.
Book Synopsis Tensile Properties of Type 316 Stainless Steel Irradiated in a Simulated Fusion Reactor Environment by :
Download or read book Tensile Properties of Type 316 Stainless Steel Irradiated in a Simulated Fusion Reactor Environment written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Tensile and fracture properties of type 316 stainless steel in the annealed and 20% cold-worked conditions were investigated to neutron fluences producing 16 dpa and 1000 at. ppM He resulting from irradiation in the High Flux Isotope Reactor. Tensile elongations remained above 6% at 350 and 450°C and 4% at 575°C. Fracture behavior has been examined in the 20% cold-worked material. At 350°C the fracture mode is unchanged by irradiation and is characterized by ductile tearing. At 450°C irradiation causes the fracture mode to change from ductile tearing to crystallographic fracture which may occur along the slip bands introduced by the cold working. At 575°C the fracture is changed from ductile transgranular to intergranular. The tensile properties observed are believed to be adequate for fusion reactor service within the values of damage parameters investigated.
Book Synopsis Effects of Radiation on Materials by : Todd R. Allen
Download or read book Effects of Radiation on Materials written by Todd R. Allen and published by ASTM International. This book was released on 2006 with total page 411 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Handbook of Nuclear Engineering by : Dan Gabriel Cacuci
Download or read book Handbook of Nuclear Engineering written by Dan Gabriel Cacuci and published by Springer Science & Business Media. This book was released on 2010-09-14 with total page 3701 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Mechanical Properties of Highly Irradiated 20 Percent Cold Worked Type 316 Stainless Steel by : ML. Hamilton
Download or read book Mechanical Properties of Highly Irradiated 20 Percent Cold Worked Type 316 Stainless Steel written by ML. Hamilton and published by . This book was released on 1982 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent experiments have extended the mechanical properties data base of 20 percent cold worked 316 stainless steel to a fluence of 1.3 x 1023 n/cm2 (E >0.1 MeV), the goal exposure of the Fast Flux Test Facility. Both uniaxial and biaxial tests were conducted on specimens of developmental cladding which were irradiated in the Experimental Breeder Reactor-II at temperatures ranging from 370°C to 650°C. Uniaxial tensile tests were conducted at strain rates ranging from 10-5/s to 10-3/s. Controlled Biaxial Strain Rate (CBSR) tests, recently developed at the Hanford Engineering Development Laboratory, were conducted only at a strain rate of 10-5/s. CBSR specimens are gas-loaded to produce a constant diametral strain rate. These tests are otherwise analogous to uniaxial tensile tests. The tensile strength and ductility of the cladding were generally in good agreement with the predicted values. These predictions were based on data obtained at lower fluences and at test temperatures ranging from 232°C to a maximum of 110°C above each of the irradiation temperatures. The temperature and fluence dependence of the yield strength was found to be consistent with the predictions of microstructurally-based models of irradiation effects at irradiation temperatures above approximately 500°C. The strengths obtained from CBSR testing were in good agreement with the correlations developed from uniaxial data only, although the ductility of the biaxial tests was generally somewhat lower. Both types of tests have shown that the cladding possesses the requisite strength and ductility for FFTF operation to goal exposure.
Book Synopsis Effects of Radiation on Materials by : Roger E. Stoller
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 Synopsis Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys by : John Moteff
Download or read book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys written by John Moteff and published by ASTM International. This book was released on 1973 with total page 560 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :ASTM International Symposium on Effects of Radiation on Structural Materials Publisher :ASTM International ISBN 13 :9780803103887 Total Pages :502 pages Book Rating :4.1/5 (38 download)
Book Synopsis Irradiation Effects on the Microstructure on Properties of Metals by : ASTM International Symposium on Effects of Radiation on Structural Materials
Download or read book Irradiation Effects on the Microstructure on Properties of Metals written by ASTM International Symposium on Effects of Radiation on Structural Materials and published by ASTM International. This book was released on 1976 with total page 502 pages. Available in PDF, EPUB and Kindle. Book excerpt:
