Tensile Properties Of 12 Cold Worked Type 316 Stainless Steel Irradiated In Ebr Ii Under Lower Dose Rate Conditions To High Fluence PDF Download

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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.


Effects of Radiation on Materials

Effects of Radiation on Materials
Author: Stan T. Rosinski
Publisher: ASTM International
Total Pages: 879
Release: 2001
Genre: Materials
ISBN: 0803128789

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Effects of Radiation on Materials

Effects of Radiation on Materials
Author: Todd R. Allen
Publisher: ASTM International
Total Pages: 411
Release: 2006
Genre: Materials
ISBN: 0803134010

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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


Nuclear Science Abstracts

Nuclear Science Abstracts
Author:
Publisher:
Total Pages: 938
Release: 1976-03
Genre: Nuclear energy
ISBN:

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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


Comprehensive Nuclear Materials

Comprehensive Nuclear Materials
Author:
Publisher: Elsevier
Total Pages: 4871
Release: 2020-07-22
Genre: Science
ISBN: 0081028660

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Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field


Tensile Property Correlations for Highly Irradiated 20 Percent Cold-Worked Type 316 Stainless Steel

Tensile Property Correlations for Highly Irradiated 20 Percent Cold-Worked Type 316 Stainless Steel
Author: NS. Cannon
Publisher:
Total Pages: 16
Release: 1979
Genre: Correlations
ISBN:

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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.


INIS Atomindeks

INIS Atomindeks
Author:
Publisher:
Total Pages: 1220
Release: 1982
Genre: Nuclear energy
ISBN:

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