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Properties of 20% Cold-worked 316 Stainless Steel Irradiated at Low Dose Rate

Properties of 20% Cold-worked 316 Stainless Steel Irradiated at Low Dose Rate
Author:
Publisher:
Total Pages: 5
Release: 2002
Genre:
ISBN:

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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


Properties of 20 % Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate

Properties of 20 % Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate
Author: H. Tsai
Publisher:
Total Pages: 12
Release: 2004
Genre: Irradiation effects
ISBN:

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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


Mechanical Properties of 20% Cold-worked 316 Stainless Steel Irradiated at Low Dose Rate

Mechanical Properties of 20% Cold-worked 316 Stainless Steel Irradiated at Low Dose Rate
Author:
Publisher:
Total Pages: 8
Release: 2001
Genre:
ISBN:

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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


Tensile Properties of 12% Cold-Worked Type 316 Stainless Steel Irradiated in EBR-II Under Lower-Dose-Rate Conditions to High Fluence

Tensile Properties of 12% Cold-Worked Type 316 Stainless Steel Irradiated in EBR-II Under Lower-Dose-Rate Conditions to High Fluence
Author: T. Yoshitake
Publisher:
Total Pages: 18
Release: 2001
Genre: 12% cold-worked type 316 stainless steel
ISBN:

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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.


Mechanical Properties of Highly Irradiated 20 Percent Cold Worked Type 316 Stainless Steel

Mechanical Properties of Highly Irradiated 20 Percent Cold Worked Type 316 Stainless Steel
Author: ML. Hamilton
Publisher:
Total Pages: 12
Release: 1982
Genre: 316 stainless steel
ISBN:

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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.


The Effect of Low Dose Rate Irradiation on the Tensile Properties and Microstructure of Austenitic Stainless Steel

The Effect of Low Dose Rate Irradiation on the Tensile Properties and Microstructure of Austenitic Stainless Steel
Author:
Publisher:
Total Pages: 11
Release: 2002
Genre:
ISBN:

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To assess the effects of long-term, low-dose-rate neutron exposure on mechanical strength and ductility, tensile properties were measured on 12% and 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 371-440 C and dose rates from 0.5-5.8 x10−7 dpa/s. These dose rates are approximately an order of magnitude lower than those of typical EBR-II test sample locations. The tensile tests for the 12% CW material were performed at 380 C and 430 C while those for the 20% CW samples were performed at 370 C. In each case, the tensile test temperature approximately matched the irradiation temperature. To help understand the tensile properties, microstructural samples with similar irradiation history were also examined. The strength and loss of work hardening increase the fastest as a function of irradiation dose for the 12% CW material irradiated at lower temperature. The decrease in ductility with increasing dose occurs more rapidly for the 12% CW material irradiated at lower temperature and the 20% cold-worked material. Post-tensile test fractography indicates that at higher dose, the 20% CW samples begin a shift in fracture mode from purely ductile to mainly small facets and slip bands, suggesting a transition toward channel fracture. The fracture for all of the 12% cold-worked samples was ductile. For both the 12% and 20% CW materials, the yield strength increases correlate with changes in void and loop density and size.


Effects of Radiation on Materials

Effects of Radiation on Materials
Author: Martin L. Grossbeck
Publisher: ASTM International
Total Pages: 767
Release: 2004
Genre: Materials
ISBN: 0803134770

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