Download or read book Determination of Creep Compliance and Creep swelling Coupling Coefficients for Neutron irradiated Titanium modified Stainless Steel at 400 Degree C written by and published by . This book was released on 1991 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep data from FFTF-MOTA at (approximately)400°C were analyzed for nine 20% cold-worked titanium-modified type 316 stainless steels, each of which exhibits a different duration for the transient regime of swelling. One of these steels was the fusion prime candidate alloy designated PCA. The others were various developmental breeder reactor heats. The analysis was based on the assumption that the B0 + DS creep model applies to these steels at this temperature. This assumption was found to be valid. A creep-swelling coupling coefficient of D (almost equal to) 0.6 x 10−2 MPa−1 was found for all steels that had developed a significant level of swelling. This result is in excellent agreement with the results of earlier studies conducted in EBR-II using annealed AISI 304L and also 10% and 20% cold-worked AISI 316 stainless steels. There appears to be some enhancement of swelling by stress, contradicting an important assumption in the analysis and leading to an apparent but misleading nonlinearity of creep with respect to stress.
Download or read book Determination of Creep Compliance and Creep swelling Coupling Coefficients for Neutron irradiated Titanium modified Stainless Steel at 00 C written by and published by . This book was released on 1991 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep data from FFTF-MOTA at ∼400°C were analyzed for nine 20% cold-worked titanium-modified type 316 stainless steels, each of which exhibits a different duration for the transient regime of swelling. One of these steels was the fusion prime candidate alloy designated PCA. The others were various developmental breeder reactor heats. The analysis was based on the assumption that the B0 + DS creep model applies to these steels at this temperature. This assumption was found to be valid. A creep-swelling coupling coefficient of D ≈ 0.6 × 10−2 MPa−1 was found for all steels that had developed a significant level of swelling. This result is in excellent agreement with the results of earlier studies conducted in EBR-II using annealed AISI 304L and also 10% and 20% cold-worked AISI 316 stainless steels. There appears to be some enhancement of swelling by stress, contradicting an important assumption in the analysis and leading to an apparent but misleading nonlinearity of creep with respect to stress.
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1992 with total page 594 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 1993 with total page 420 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics Briefs written by and published by . This book was released on 1993 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Metals Abstracts written by and published by . This book was released on 1993 with total page 1218 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Annual Index written by and published by . This book was released on 1992 with total page 1220 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1992 with total page 1266 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reanalysis of Swelling and Irradiation Creep Data on 316 Type Stainless Steels Irradiated in the FFTF and Ph nix Fast Reactors written by MB. Toloczko and published by . This book was released on 2000 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: In comparing results of irradiation creep experiments conducted by researchers in France and those by researchers at Pacific Northwest National Laboratory in the United States, quite different values for the creep-swelling coupling coefficient were reported. The differing coefficients complicated the understanding of the growing data base on irradiation creep. However, upon careful consideration, the French and US results showed key differences in experimental technique and analysis. The French and US irradiation creep experiments were conducted with several important differences that were initially thought to be of little consequence. One difference was related to whether stress-free swelling or stress-enhanced swelling was measured and used in calculating the creep strains. Inspection of irradiation creep results published by the French also showed their technique for extracting the creep-swelling coupling coefficient was different than that used by the present authors. In an effort to better understand the origin of the differing creep coefficients, data from the French and US experiments was reanalyzed taking into account these differences. In performing this reanalysis, completely consistent results were obtained.
Download or read book Irradiation induced Creep in 316 and 304L Stainless Steels Fast Neutrons written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent results are presented from the in-reactor creep experiments that are being conducted by Argonne National Laboratory. The experiments consist of four subassemblies that contain helium-pressurized as well as unstressed capsules of 316 and 304L stainless steels in several metallurgical conditions. Experiments are being irradiated in row 7 of the EBR-II sodium-cooled fast breeder reactor. Three of the subassemblies are being irradiated at temperatures near 400°C, and the fourth subassembly is being irradiated at a temperature of 550°C. Creep and swelling strains were determined by profilometer measurements on the full length of the capsules after each irradiation cycle. The accumulated neutron dose on the 304L capsules at 385°C was 45 dpa; on the 316 capsules at 400°C, 40 dpa; and on the 316 capsules at 550°C, 25 dpa. It was found that the in-reactor creep rates were linearly dependent on hoop stress, with the exception being capsules of 316 stainless steel that had been given long-term carbide aging treatment and then irradiated at 550°C. Those capsules exhibited much higher creep and swelling rates than their unaged counterparts. For the metallurgical conditions where significant swelling was observed (solution-annealed 304L and aged 316 stainless steels), it was found that the in-reactor creep rates were readily fit to a model that related the creep rates to accumulated swelling. Additionally, it was found that the stress-normalized creep rate for 20%-cold-worked 316 stainless steel at a temperature of 550°C was 1.6 times that observed at 400°C.
Download or read book Effect of Fast Neutron Irradiation on the Creep rupture Properties of Type 304 Stainless Steel at 600 C written by E. E. BLOOM and published by . This book was released on 1971 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Creep and Swelling of AISI 316 to Exposures of 130 Dpa at 385 to 400 C written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The creep and swelling of AISI 316 stainless steel have been studied at 385 to 400°C in EBR-II to doses of 130 dpa. Most creep capsules were operated at constant stress and temperature but mid-life changes in these variable were also made. This paper concentrates on the behavior of the 20% cold-worked condition but five other conditions were also studied. Swelling at less than or equal to00°C was found to lose the sensitivity to stress exhibited at higher temperatures while the creep rate was found to retain linear dependencies on both stress and swelling rate. The creep coefficients extracted at 400°C agree with those found in other experiments conducted at higher temperatures. In the temperature range of less than or equal to400°C, swelling is in the recombination-dominated regime and the swelling rate falls strongly away from the approx. 1%/dpa rate observed at higher temperatures. These lower rates of creep and swelling, coupled with the attainment of high damage levels without failure, encourage the use of AISI 316 in the construction of water-cooled fusion first walls operating at temperatures below 400°C. 23 refs., 8 figs.
Download or read book Effect of Fast Neutron Irradiation on the Creep rupture Properties of Type 304 Stainless Steel at 600 C written by and published by . This book was released on 1971 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of Neutron Irradiation on the Creep rupture Properties of Type 316 Stainless steel Tubes written by and published by . This book was released on 1969 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of irradiation in the Dounreay Fast Reactor and the Dounreay Materials Testing Reactor on the creep-rupture properties of Type 316 stainless-steel tubing have been investigated. DFR irradiation produced a loss of rupture ductility but, in general, no change in creep strength in 650 deg C biaxial tests of solution-treated material. Cold-worked tubes suffered a loss of 550 deg C creep strength. Irradiation of solution-treated tubes at 650 deg C in DMTR caused a severe loss of high-temperature ductility and a ten-fold reduction of creep rate both during and after irradiation; it is possible that an irradiation-induced carbide precipitation process is responsible for the increase of creep strength. (auth).
Download or read book Effects of Neutron Irradiation on Creep Rupture Properties of Type 316 Stainless Steel Tubes written by I. P. Bell and published by . This book was released on 1969 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of irradiation in the Dounreay Fast Reactor and the Dounreay Materials Testing Reactor on the creep-rupture-properties of Type 316 stainless steel tubing were investigated. DFR irradiation produced a loss of rupture ductility but, in general, no change in creep strength in 650 C biaxial tests of solution-treated material. Cold-worked tubes suffered a loss of 550 C creep strength. Irradiation of solution-treated tubes at 650 C in DMTR caused a severe loss of high-temperature ductility and a tenfold reduction of creep rate both during and after irradiation. It is possible that an irradiation-induced carbide precipitation process is responsible for the increase of creep strength.
Download or read book Neutron Irradiation Creep at 100 C on 316L AMCR and Welded 316L Stainless Steel Alloys written by H. Hausen and published by . This book was released on 1999 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: We performed measurements on the elongation of many different austentic stainless steel alloys irradiating at 100°C in a low flux channel of the High Flux Reactor at Petten varying the applied stress between zero and 300 MPa. We irradiated in total 98 samples in two irradiation rigs. Of these samples only 26 samples could be tested up to a dose of 2.1 dpa, and 13 samples up to a dose of 0.21 dpa. The steels tested are listed in Table I. In the second irradiation rig four TIG-welded samples and one EB-welded sample were irradiated.
Download or read book Effects of Neutron Irradiation on Fatigue and Creep Fatigue Crack Propagation in Type 316 Stainless Steel at 649 C written by DJ. Michel and published by . This book was released on 1981 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: The fatigue and creep-fatigue crack propagation performance of Type 316 stainless steel has been investigated following fast neutron (n) irradiation to fluence levels of ~1.5 x 1022 and ~5 x 1022 n/cm2 (>0.1 MeV), ~6 and 26 displacements per atom (dpa), respectively, at 649°C. The purpose of this work was to evaluate the effects of neutron fluence and temperature on the crack propagation resistance and failure mode of the steel. The results from fatigue tests of the annealed steel show that irradiation to both fluence levels at 649°C produced no significant effect on the crack propagation rate when compared with unirradiated steel tested at 649°C. For the 20 percent cold-worked steel, however, irradiation to the lower fluence level increased the crack propagation rate while at the higher fluence level the crack propagation rate was only slightly increased relative to the unirradiated material. For tests conducted using creep-fatigue cycling, the effect of a 1-min hold time at the maximum cyclic load was to produce a marked increase in the crack propagation rate of the annealed steel irradiated to the lower fluence level. At the higher fluence level, the inclusion of a 2-min hold time in the creep-fatigue cycle resulted in a further increase in the crack propagation rate. The effect of a 1-min hold time in the irradiated, 20 percent cold-worked steel was to significantly increase the crack propagation rates, particularly at the low fluence level at 649°C. Scanning electron microscope examination of the fracture surfaces of the tested specimens revealed that the failure mode of the specimens which exhibited increased crack propagation rates was primarily intergranular while a transgranular mode was observed for specimens with lower crack propagation rates. The results point toward a synergistic relationship between thermomechanical history, precipitate formation, and hold time effects as the responsible mechanism for the crack propagation performance.
