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Book Effects of Low Temperature Neutron Irradiation on Deformation Behavior of Austenitic Stainless Steels

Download or read book Effects of Low Temperature Neutron Irradiation on Deformation Behavior of Austenitic Stainless Steels written by and published by . This book was released on 1996 with total page 203 pages. Available in PDF, EPUB and Kindle. Book excerpt: An austenitic stainless steel, designated 316LN-IG, has been chosen for the first wall/shield (FW/S) structure for the International Thermonuclear Experimental Reactor (ITER). The proposed operational temperature range for the structure (100 to 250°C) is below the temperature regimes for void swelling (400-600°C) and for helium embrittlement (500-700°C). However, the proposed neutron dose is such that large changes in yield strength, deformation mode, and strain hardening capacity could be encountered which could significantly affect fracture properties. Definition of the irradiation regimes in which this phenomenon occurs is essential to the establishment of design rules to protect against various modes of failure.

Book Temperature Dependence of the Deformation Behavior of 316 Stainless Steel After Low Temperature Neutron Irradiation

Download or read book Temperature Dependence of the Deformation Behavior of 316 Stainless Steel After Low Temperature Neutron Irradiation written by and published by . This book was released on 1996 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of low temperature neutron irradiation on the tensile behavior of 316 stainless steel have been investigated. A single heat of solution annealed 316 was irradiated to 7 and 18 dpa at 60, 200, 330, and 400°C. The tensile properties as a function of dose and as a function of temperature were examined. Large changes in yield strength, deformation mode, strain to necking, and strain hardening capacity were seen in this irradiation experiment. The magnitudes of the changes are dependent on both irradiation temperature and neutron dose. Irradiation can more than triple the yield strength over the unirradiated value and decrease the strain to necking (STN) to less than 0.5% under certain conditions. A maximum increase in yield strength and a minimum in the STN occur after irradiation at 330°C but the failure mode remains ductile.

Book Temperature Dependence of the Deformation Behavior of Type 316 Stainless Steel After Low Temperature Neutron Irradiation

Download or read book Temperature Dependence of the Deformation Behavior of Type 316 Stainless Steel After Low Temperature Neutron Irradiation written by and published by . This book was released on 1996 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: A single heat of solution annealed 316 ss was irradiated to 7 and 18 dpa at 60, 200, 330, and 400 C. Tensile properties were studied vs dose and temperature. Large changes in yield strength, deformation mode, strain to necking (STN), and strain hardening capacity were seen. Magnitude of the changes are dependent on both irradiation temperature and neutron dose. Irradiation can more than triple the yield strength and decrease STN to

Book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys

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:

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by R. K. Nanstad and published by ASTM International. This book was released on 1999 with total page 1135 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Neutron Irradiations at Temperatures Below 500  C on the Properties of Cold Worked 316 Stainless Steels

Download or read book Effects of Neutron Irradiations at Temperatures Below 500 C on the Properties of Cold Worked 316 Stainless Steels written by JC. Van Duysen and published by . This book was released on 1994 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: Many components used in the pressure vessel of French pressurized water reactors are made of austenitic stainless steels : 316L for screws, 304L for core barrel and baffle assembly, etc. Among these components, the most irradiated ones undergo an average damage rate of about 1 dpa/an at temperatures which may reach about 400°C. Such irradiations may have very detrimental effects on the in-service behaviour of austenitic steels. In order to forecast these effects, Electricité de France has defined important programmes of studies. In the framework of these programmes, we have carried out a review concerning the effects of irradiations at relatively low temperatures (i. e. 500°C) on cold-worked 316 stainless steel. We were particularly interested in the evolution of microstructure as well as tensile (with or without notch), creep, fatigue (with or without creep) and fracture toughness properties. In some cases, we have also analysed the influence of cold-work level, irradiation temperature and test temperature. For some mechanical properties, the data was sufficient to qualitatively predict the properties of cold worked 316 stainless steels after long -- term irradiations under PWR conditions.

Book Effects of Radiation on Materials

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 Effect of Fast neutron Irradiation on Plastic Deformation of Type 304 Stainless Steel

Download or read book Effect of Fast neutron Irradiation on Plastic Deformation of Type 304 Stainless Steel written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Plastic deformation of EBR-II-irradiated Type 304 stainless steel was investigated by a stress-relaxation method. The stress-strain-rate relationships for the irradiated specimens at room temperature are concave upward, which are similar to those for the unirradiated specimens. However, concave downward behavior in the stress-strain-rate relationships were observed at much lower temperatures for the irradiated specimens in contrast to the unirradiated specimens. These results were analyzed succccessfully using Hart's mechanical equation-of-state concept. It was found that the hardness sigma*, which is the minimum stress necessary for the dislocation to overcome obstacles without thermal activation, increases linearly with fast-neutron fluence. This increase in sigma* is consistent with so-called ''irradiation hardening.'' In addition, resistance to dislocation glide, which is quantitatively measured in terms of sigma0, was observed to decrease linearly with fast-neutron fluence. The decrease in sigma0 can be attributed to a decrease of solute drag due to irradiation-induced solute segregation.

Book Evaluation of Low Temperature Swelling in Austenitic Stainless Steels

Download or read book Evaluation of Low Temperature Swelling in Austenitic Stainless Steels written by Y. Katoh and published by . This book was released on 1999 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Major portions of structural materials of near-term fusion blankets and light water reactor core components are subject to neutron irradiation at low temperatures and low fluxes compared to those in typical void swelling studies using fast reactors. Observed swelling in austenitic stainless steels at temperatures below 673K are generally very small under typical fast reactor irradiation conditions, however, the amount of swelling might be significantly influenced by neutron flux, helium generation rate, etc. In this work, using a reaction rate theory model of swelling, the influences of such key irradiation parameters on low temperature swelling behavior in austenitic stainless steels will be demonstrated to aid the evaluation of swelling at low temperature and low neutron flux conditions.

Book Stress Relaxation in Stainless Steel During Irradiation

Download or read book Stress Relaxation in Stainless Steel During Irradiation written by J. Walter Joseph and published by . This book was released on 1959 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Irradiation Effects in Cladding and Structural Materials

Download or read book Irradiation Effects in Cladding and Structural Materials written by Spencer Harrison Bush and published by . This book was released on 1965 with total page 250 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Structural Alloys for Nuclear Energy Applications

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.

Book Effects of Hydrogen on the Deformation Behavior of Austenitic Stainless Steel

Download or read book Effects of Hydrogen on the Deformation Behavior of Austenitic Stainless Steel written by Daniel Parampil Abraham and published by . This book was released on 1993 with total page 378 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Effect of Nuclear Radiation on Structural Metals

Download or read book The Effect of Nuclear Radiation on Structural Metals written by Frederic R. Shober and published by . This book was released on 1961 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 724 pages. Available in PDF, EPUB and Kindle. Book excerpt: Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.

Book Postirradiation Tensile Behavior of 300 Series Stainless Steels

Download or read book Postirradiation Tensile Behavior of 300 Series Stainless Steels written by J. J. Holmes and published by . This book was released on 1969 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of neutron irradiation on the tensile properties of several austenitic stainless steels are considered over a wide fluence and temperature range. At low fluence levels (about 1020 neutrons (n)/cm2, E > 1 MeV), displacement damage results in radiation hardening if the irradiation and test temperatures are below one half the absolute melting temperature (0.5 Tm) of the steel. Above 0.5 Tm, hardening no longer exists, but a ductility loss due to helium embrittlement is observed. The temperature above which radiation hardening is no longer significant increases with increasing fluence. Elevated temperature hardening after fast reactor irradiations is the result of void formation. The hardening observed after thermal reactor irradiations appears to be due to the formation of gas filled bubbles, but the nature of the gas is not clear.