Download or read book Tensile Property Correlations for Highly Irradiated 20 Percent Cold Worked Type 316 Stainless Steel written by NS. Cannon and published by . This book was released on 1979 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent experiments on developmental fast-flux test facility (FFTF) cladding (20 percent cold-worked Type 316 stainless steel) have extended the data base to a fast neutron fluence of 8.4 x 1022 neutrons (n)/cm2 (E > 0.1 MeV). The specimens were irradiated in the experimental breeder reactor-II (EBR-II) at temperatures ranging from 371 to 816°C, although peak fluence levels were attained on specimens irradiated near 371 and 649°C only. Tension tests were performed at 232°C, near the irradiation temperature, and, in some cases, above the irradiation temperature. Test specimen strain rates ranged from 4 x 10 -5/s to 4 x 10-2/s.
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.
Download or read book Mechanical Properties of Highly Irradiated 20 Percent Cold worked Type 316 Stainless Steel written by and published by . This book was released on 1982 with total page 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 speciments 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.
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
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
Download or read book Tensile Properties and Swelling of 20 cold worked Type 316 Stainless Steel Irradiated in HFIR written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Immersion density and elevated-temperature tensile properties were determined on 20%-cold-worked type 316 stainless steel irradiated in the HFIR at approximately 285, 370, 470, 560, and 620°C to fluences of 1.8 to 6.2 x 1026 neutrons/m2 (> 0.1 MeV), which resulted in displacement damage levels of 16 to 54 dpa and helium concentrations of 900 to 3300 at. ppM. Tensile tests were done at temperatures near the estimated irradiation temperatures. Swelling increased with increasing irradiation temperature to a maximum of 2.1% at 620°C. Irradiation at the lowest temperature (285 and 370°C) increased the strength. At the higher irradiation temperatures, the strength decreased during irradiation. Ductility generally reflected the strength behavior: an increase in strength resulted in a descrease in ductility. When the present data are compared with previously published data, there is good agreement with one exception. Previous experiments showed a large decrease in ductility when irradiated at 600°C and tested at 575°C that was not observed in the present tests. There was also good agreement between HFIR-irradiated steel and literature data for EBR-II-irradiated steel.
Download or read book Effects of Radiation on Structural Materials written by James A. Sprague and published by ASTM International. This book was released on 1979 with total page 700 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:
Download or read book Tensile Properties of 20 Cold worked Titanium modified Type 316 Stainless Steel Irradiated in HFIR written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An alloy of type 316 stainless steel with the addition of 0.23% Ti (316 + Ti) has been irradiated in the 20% cold-worked condition in the HFIR (a mixed fast and thermal neutron spectrum reactor) and tested near the irradiation temperature in the range of 300 to 600°C. Tensile tests were performed following irradiation to fluence levels of 0.63 to 2.1 x 1026 n/m2 (E> 0.1 MeV) and helium levels of 200 to 1000 at. ppM. The 316 + Ti exhibited higher strength and lower ductility than similarly irradiated type 316 stainless steel (316 SS). However, the tensile elongation of 316 + Ti tends to saturate with increasing fluence at 575°C whereas the elongation of 316 SS continues to fall for the fluences investigated. Reduction of area is similar for the two alloys, and 316 + Ti shows completely ductile rupture at 450°C and below. The differences in strength and ductility are attributed to the influence of TiC precipitates trapping helium in the matrix.
Download or read book Effect of Cold Work on Tensile Behavior of Irradiated Type 316 Stainless Steel written by RL. Klueh and published by . This book was released on 1987 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effect of various levels of cold work on the tensile behavior of Type 316 stainless steel was investigated. Tensile specimens were irradiated in the Oak Ridge Research Reactor (ORR) at 250, 290, 450, and 500°C to produce a displacement damage of ~5 displacements per atom (dpa) and 40 atomic ppm He. Irradiation at 250 and 290°C caused an increase in yield stress and ultimate tensile strength and a decrease in ductility relative to unaged and thermally aged controls. The changes were greatest for the 20%-cold-worked steel and lowest for the 50%-cold-worked steel. Irradiation at 450°C caused a slight decrease in strength for all cold-worked conditions relative to the aged material. A large decrease was observed at 500°C, with the largest decrease occurring for the 50%-cold-worked specimen. No bubble, void, or precipitate formation was observed for specimens examined by transmission electron microscopy (TEM). The irradiation hardening was correlated with Frank-loop and "black-dot" damage. A strength decrease at 500°C was correlated with dislocation network recovery. Comparison of tensile and TEM results from ORR-irradiated steel with those from steels irradiated in the High Flux Isotope Reactor and the Experimental Breeder Reactor indicated consistent strength and microstructure changes.
Download or read book Effect of Cold Work on Tensile Behavior of Irradiated Type 316 Stainless Steel written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Tensile specimens were irradiated in ORR at 250, 290, 450, and 500°C to produce a displacement damage of approx. 5 dpa and 40 at. ppM He. Irradiation at 250 and 290°C caused an increase in yield stress and ultimate tensile strength and a decrease in ductility relative to unaged and thermally aged controls. The changes were greatest for the 20%-cold-worked steel and lowest for the 50%-cold-worked steel. Irradiation at 450°C caused a slight relative decrease in strength for all cold-worked conditions. A large decrease was observed at 500°C, with the largest decrease occurring for the 50%-cold-worked specimen. No bubble, void, or precipitate formation was observed for specimens examined by transmission electron microscopy (TEM). The irradiation hardening was correlated with Frank-loop and ''black-dot'' loop damage. A strength decrease at 500°C was correlated with dislocation network recovery. Comparison of tensile and TEM results from ORR-irradiated steel with those from steels irradiated in the High Flux Isotope Reactor and the Experimental Breeder Reactor indicated consistent strength and microstructure changes.
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1984 with total page 1278 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 Tensile Properties of 12 Cold Worked Type 316 Stainless Steel Irradiated in EBR II Under Lower Dose Rate Conditions to High Fluence written by T. Yoshitake and published by . This book was released on 2001 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of lower-dose-rate irradiation on the tensile properties of 12% cold-worked type 316 stainless steel hexagonal ducts which were irradiated in the outer rows of EBR-II were investigated. Tension tests were conducted on a total of seventeen irradiation conditions. Fractographic examinations were performed on four irradiation conditions which were selected based on the results of tension tests. The results of the tension tests and fractographic examinations showed that the 316 stainless steel hexagonal ducts exhibited irradiation hardening typical to 316 stainless steels irradiated at similar temperatures and retained respectable ductility after the irradiation. There was no significant effect of dose rate on tensile properties for the range of irradiation conditions of this study.
Download or read book Effect of Fast Reactor Irradiation on the Tensile Properties of 20 Percent Cold Worked Type 316 Stainless Steel written by RL. Fish and published by . This book was released on 1976 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fast neutron irradiation effects on the tensile properties of 20 percent cold-worked Type 316 stainless steel are presented to fluences of 3.6 x 1022 neutrons (n)/cm2, E > 0.1 MeV (3.6 x 1026 n/m2, E > 16 fJ), at irradiation temperatures of 700 to 1125°F (644 to 880 K). The tests were performed over the range of room temperature to 1600°F (1144 K) employing strain rates of 1.82 x 10-3 to 1.82/min (3 x 10-5 to 3 x 10-2/s).
Download or read book Neutron Energy Dependent Damage Functions for Tensile Properties of 20 Percent Cold Worked Type 316 Stainless Steel written by RL. Simons and published by . This book was released on 1976 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Material property measurements from test reactor irradiations cannot always be applied directly to design reactor irradiation conditions because of differences in neutron spectra. A semi-empirical damage function can be derived from the test reactor data for a particular property to describe the damage effectiveness of neutrons as a function of their energies. Such functions have been derived for strength and ductility parameters of 20 percent cold-worked Type 316 stainless steel for irradiation temperatures of 393, 493, and 593°C (740, 920, and 1100°F). Both fast and thermal reactor data were used in the analysis. Quantitative conclusions from this analysis were limited by the lack of data; however, damage functions for tensile properties of 20 percent cold-worked Type 316 stainless steel irradiated at 393 and 493°C (740 and 920°F) appear to be consistent with the displacement cross section for stainless steel. At 593 °C (1100°F) the ductility damage functions show substantial deviation from the displacement cross shape when both fast and thermal reactors are included in the analysis. The latter damage functions were found to be consistent with the correlation of ductility with the square root of the product of displacements and helium concentration. Examples of application to fast reactors and fusion reactors are given.
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:
