Download or read book Effect of Neutron Irradiation on Mechanical Properties of Ferritic Steels written by and published by . This book was released on 1995 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Effect of neutron radiation exposure was investigated in various ferritic steels with the main emphasis being the effects of thermal neutrons on radiation hardening. Pure iron of varied grain sizes was also used for characterizing the grain size effects on the source hardening before and after neutron irradiation. While many steels are considered in the overall study, the results on 1020, A516 and A588 steels are emphasized. Radiation hardening due to fast neutrons was seen to be sensitive to the composition of the steels with A354 being the least resistant and A490 the least sensitive. Majority of the radiation hardening stems from friction hardening, and source hardening term decreased with exposure to neutron radiation apparently due to the interaction of interstitial impurities with radiation produced defects. Inclusion of thermal neutrons along with fast resulted in further decrease in the source hardening with a slight increase in the friction hardening which revealed a critical grain size below which exposure to total (fast and thermal) neutron spectrum resulted in a slight reduction in the yield stress compared to the exposure to only fast neutrons. This is the first time such a grain size effect is reported and this is shown to be consistent with known radiation effects on friction and source hardening terms along with the observation that low energy neutrons have a nonnegligible effect on the mechanical properties of steels. In ferritic steels, however, despite their small grain size, exposure to total neutron spectrum yielded higher strengths than exposure to only fast neutrons. This behavior is consistent with the fact that the source hardening is small in these alloys and radiation effect is due only to friction stress.

Download or read book Effects of Neutron Irradiation on Mechanical Properties of Ferritic Steels and Irons written by Atomic Energy of Canada Limited and published by . This book was released on 1958 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of 14 MeV Neutron Irradiations on Mechanical Properties of Ferritic Steels written by A. Kohyama and published by . This book was released on 1987 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Seven kinds of 9Cr-2Mo type ferritic steels were irradiated at 300, 473, and 673 K with 14-MeV neutrons from Rotating Target Neutron Source II (RTNS-II) at Lawrence Livermore National Laboratory (LLNL). The maximum neutron fluence was 4 x 1022 n/m2. Post-irradiation mechanical property tests, microVickers hardness tests, microtension tests, and micro-bulge tests were performed. Microstructural evolutions under irradiation were examined by transmission electron microscopy.

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).

Download or read book A SURVEY OF THE EFFECTS OF NEUTRON IRRADIATION ON THE IMPACT AND OTHER MECHANICAL PROPERTIES OF PRESSURE VESSEL STEELS FOR THE SM 2 REACTOR written by and published by . This book was released on 1960 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A literature survey on the effects of neutron irradiation on impact and other mechanical properties of both ferritic steels and austenitic stainless steels is presented. The materials studied included carbon and low alloy steels such as: ASTM A-212B, ASTM A-201, ASTM A-301B (CR-Mo), ASTM A-106 (coarse and fine grained), ASTM A-285, ASTM A-302B (Mn-Mo), ASTM A-353, ASTM A-203, Grade D, E-7016 carbon steel weld metal, USS Carilloy T-1, HY-65, and HY-80. Types 304 and 347 stainless steels were investigated as representative austenitic materials which might be used in pressure vessel construction. An evaluation was made of the irradiation induced changes in the mechancal properties of the above materials. The ferritic steels were evaluated primarily on the basis of increases in transition temperature due to irradiation and decreases in the amount of maximum energy absorbed prior to ductile failure. Factors such as industrial experience, changes in other mechanical properties, and the susceptibility of these materials to temper embrittlement were considered. Austenitic stainless steels were evaluated on the basis of post-irradiation and low temperature impact strength and on irradiation induced changes in other mechanical properties. It is concluded that austenitic stainless steels are capable of resisting harmful property damage at integrated neutron fluxes> 1 Mev of at least 1 to 2 x 10/sup 21/ nvt. Most carbon or low alloy steels with the exception of ASTM A-212B, were subject to severe property damage at exposures in excess of 1 x 10/sup 19/ nvt. With the application of special reactor operating procedures, it was determined that ASTM A-212B will be satisfactory at integrated neutron fluxes up to 5 x 10/sup 19/ nvt. (auth).

Download or read book Effect of Neutron Irradiation on Mechanical Properties of AISI Type 347 Stainless Steel written by M. Kangilaski and published by . This book was released on 1967 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Changes in mechanical properties induced by irradiation of AISI Type 347 stainless steel at about 60 C were determined after integrated fast-flux (>1 Mev) exposures of 1.6 x 1022 and 2.1 x 1022 n/cm2. Tension tests were performed at room temperature, 316, and 750 C. The results indicated that the ultimate tensile strength and yield strength were greater after irradiation, with the yield strength showing the greater increase. After an exposure of 2.1 x 1022 n/cm2, the ratio of yield strength to ultimate strength was approximately 1. The decreases in ductility as measured by total and uniform elongation at 20 C were about the same magnitude for both levels of irradiation. The ductility at 316 C continued to decrease as a function of increasing neutron exposure. Radiation-induced property changes differed only slightly from those observed after irradiation to 5.5 x 1021 n/cm2 with the exception of the uniform and the total elongation at 316 C, suggesting that saturation of displacement damage occurred prior to this exposure. The fracture mode for both unirradiated and irradiated specimens was transgranular. Annealing of irradiated specimens for 1 hr at 982 C restored the preirradiation mechanical properties at 316 C. A severe reduction in ductility was noted for specimens tested at 750 C after irradiation to 2.1 x 1022 n/cm2, showing only about 0.5 per cent as uniform and total elongation. The fracture mode was intergranular. Annealing for 1 hr at 982 and 1350 C did not change the as-irradiated ductility.

Download or read book Helium Effects on the Mechanical Properties of Neutron irradiated Cr Mo Ferritic Steels written by and published by . This book was released on 1990 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: In the first wall of a fusion rector, large amounts of transmutation helium will be produced simultaneously with the displacement damage caused by high-energy neutrons from the fusion reaction. One method used to simulate irradiation effects for ferritic steels is to add nickel to the steels and irradiate them in a mixed-spectrum reactor. Fast neutrons in the spectrum produce displacement damage, while transmutation helium is produced by a two-step reaction of 58Ni with thermal neutrons. This technique has been used to investigate the effect of helium on tensile properties and toughness. Results from these studies are summarized.

Download or read book Radiation Effects on Toughness of Ferritic Steels for Reactor Vessels written by L. P. Trudeau and published by . This book was released on 1964 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Damage of Ferritic written by and published by . This book was released on 1997 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Ferritic/martensitic steels were chosen as candidates for future fusion power plants because of their superior swelling resistance and better thermal properties than austenitic stainless steels. For the same reasons, these steels are being considered for the target structure of a spallation neutron source, where the structural materials will experience even more extreme irradiation conditions than expected in a fusion power plant first wall (i.e., high-energy neutrons that produce large amounts of displacement damage and transmutation helium). Extensive studies on the effects of neutron irradiation on the mechanical properties of ferritic/martensitic steels indicate that the major problem involves the effect of irradiation on fracture, as determined by a Charpy impact test. There are indications that helium can affect the impact behavior. Even more helium will be produced in a spallation neutron target material than in the first wall of a fusion power plant, making helium effects a prime concern for both applications. 39 refs., 10 figs.

Download or read book Irradiation Effects on Mechanical Properties of High Manganese Steels written by H. Kodaka and published by . This book was released on 1990 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Several high-manganese austenitic steels and ferritic steels were studied by means of mechanical tests in order to develop materials for reduction of radioactivity of the first wall material after irradiation in a fusion reactor. After testing the commercial high manganese austenitic steels (that is, Fe-22%Mn-13%Cr-5%Ni), a new type of high manganese austenitic steels (that is, Fe-17%Mn-6.5%Cr-4.5%Si and Fe-22%Mn-6.5%Cr-4.5%Si-0.2N) was developed. Tensile tests were performed using miniature specimens in the temperature range between 4 and 500 K. Instrumented Charpy impact tests were also performed using quarter-size specimens at 77 to 550 K. It was found that the new steels show high strength and good ductility before irradiation. Neutron irradiations were carried out in the Kyoto University Reactor (KUR) and the Japan Material Testing Reactor (JMTR) reactors. After neutron irradiation up to 1 x 1020 n/cm2, the high-manganese steels and high silicon-manganese steels still showed high strength and good ductility.

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:

Download or read book Report on the Effects of Neutron Radiation on Structural Materials written by M. Kangilaski and published by . This book was released on 1967 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Neutron Irradiation on the Microstructure and Mechanical Properties of the Heat Affected Zone of Stainless Steel Welds written by Raluca Stoenescu and published by . This book was released on 2005 with total page 153 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Temperature Effects on the Mechanical Properties of Candidate SNS Target Container Materials After Proton and Neutron Irradiation written by and published by . This book was released on 2001 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report presents the tensile properties of EC316LN austenitic stainless steel and 9Cr-2WVTa ferritic/martensitic steel after 800 MeV proton and spallation neutron irradiation to doses in the range 0.54 to 2.53 dpa. Irradiation temperatures were in the range 30 to 100 C. Tensile testing was performed at room temperature (20 C) and 164 C to study the effects of test temperature on the tensile properties. Test materials displayed significant radiation-induced hardening and loss of ductility due to irradiation. The EC316LN stainless steel maintained notable strain-hardening capability after irradiation, while the 9Cr-2WVTa ferritic/martensitic steel posted negative strain hardening. In the EC316LN stainless steel, increasing the test temperature from 20 C to 164 C decreased the strength by 13 to 18% and the ductility by 8 to 36%. The tensile data for the EC316LN stainless steel irradiated in spallation conditions were in line with the values in a database for 316 stainless steels for doses up to 1 dpa irradiated in fission reactors at temperatures below 200 C. However, extra strengthening induced by helium and hydrogen contents is evident in some specimens irradiated to above about 1 dpa. The effect of test temperature for the 9Cr-2WVTa ferritic/martensitic steel was less significant than for the EC316LN stainless steel. In addition, strain-hardening behaviors were analyzed for EC316LN and 316L stainless steels. The strain-hardening rate of the 316 stainless steels was largely dependent on test temperature. It was estimated that the 316 stainless steels would retain more than 1% true stains to necking at 164 C after irradiation to 5 dpa. A calculation using reduction of area (RA) measurements and stress-strain data predicted positive strain hardening during plastic instability.

Download or read book The Effect of Fast Neutron Irradiation on the Mechanical Properties of Some Stainless and Low Alloy Steels written by R. R. Hosbons and published by . This book was released on 1969 with total page 41 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by N. H. Packan and published by ASTM International. This book was released on 1990 with total page 679 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annotation Effects of Radiation on Materials: Fourteenth International Symposium was presented at Andover, MA, June 1988. The symposium was sponsored by ASTM Committee E-10 on Nuclear Technology and Applications. The papers from the first three days of the symposium appear in the two volumes of this publication. Volume I encompasses radiation damage- induced microstructures; point defect, solute, and gas atom effects; atomic-level measurement techniques; and applications of theory. Volume II includes mechanical behavior, all papers dealing with pressure-vessel steels, breeder reactor components, dosimetry, and nuclear fuels. The fourth day of the symposium was devoted to the single topic of reduced-activation materials (see TK9204). The two volumes are separately sold at $127 and $128 respectively; each is independently indexed. Annotation copyrighted by Book News, Inc., Portland, OR.

Download or read book The Effect of Fast Neutron Irradiation on the Mechanical Properties of Some Stainless and Low Alloy Steels written by Hosbons, R. R and published by Chalk River, Ont. : Atomic Energy of Canada Limited. This book was released on 1969 with total page 41 pages. Available in PDF, EPUB and Kindle. Book excerpt: