Download or read book IRRADIATION CREEP AND SWELLING OF ANNEALED TYPE 304L STAINLESS STEEL AT APPROXIMATELY 390 DEGREE C AND HIGH NEUTRON FLUENCE written by D.L. PORTER. and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Response to Annealing and Reirradiation of AISI 304L Stainless Steel Following Initial High Dose Neutron Irradiation in EBR II written by GL. McVay and published by . This book was released on 1981 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: The object of this study was to measure the stability of irradiation-induced microstructure upon annealing and, by selectively annealing out some of these features and reirradiating the material, it was expected that information could be gained concerning the role of microstructural changes in the void swelling process. Transmission electron microscopic examinations of isochronally annealed (200 to 1050°C) AISI 304L stainless steel, which had been irradiated at approximately 415°C to a fast (E > 0.1 MeV) neutron fluence of approximately 5.1 x 1026 neutrons/m2, verified that the two-stage hardness recovery with temperature was related to a low-temperature annealing of dislocation structures and a higher-temperature annealing of voids and solute redistribution. Voids which remained after annealing at 1054°C reflected void coalescence and were quite stable due to the development of long diffusion distances between vacancy sinks. Reirradiation of material which had been annealed for 1 h at 700°C, resulting in dislocation anneal and solute redistribution, while undisturbing the void population, produced the surprising result that the material swelled at rates equal to those of a material which had never been previously irradiated. These results confirmed that void nucleation alone does not determine swelling rates in 304L stainless steel. Moreover, contrasting quantitative microstructural information observed in 304L stainless steel with that previously observed in AISI 316 stainless steel helped to demonstrate that the observed differences in swelling behavior are likely to be related to differences in concentrations of solute elements.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 752 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.

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 Government Reports Announcements Index written by and published by . This book was released on 1990 with total page 1356 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Response to Annealing and Reirradiation of AISI 304L Stainless Steel Following Initial High dose Neutron Irradiation in EBR II LMFBR written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The object of this study was to measure the stability of irradiation-induced microstructure upon annealing and, by selectively annealing out some of these features and reirradiating the material, it was expected that information could be gained concerning the role of microstructural changes in the void swelling process. Transmission electron microscopic examinations of isochronally annealed (200 to 1050°C) AISI 304L stainless steel, which had been irradiated at approximately 415°C to a fast (E> 0.1 MeV) neutron fluence of approximately 5.1 x 1026n/m2, verified that the two-stage hardness recovery with temperatures was related to a low temperature annealing of dislocation structures and a higher temperature annealing of voids and solute redistribution.

Download or read book Heat to heat Variability of Irradiation Creep and Swelling of HT9 Irradiated to High Neutron Fluence at 400 600 degrees C written by and published by . This book was released on 1996 with total page 189 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep data on ferritic/martensitic steels are difficult and expensive to obtain, and are not available for fusion-relevant neutron spectra and displacement rates. Therefore, an extensive creep data rescue and analysis effort is in progress to characterize irradiation creep of ferritic/martensitic alloys in other reactors and to develop a methodology for applying it to fusion applications. In the current study, four tube sets constructed from three nominally similar heats of HT9 subjected to one of two heat treatments were constructed as helium-pressurized creep tubes and irradiated in FFTF-MOTA at four temperatures between 400 and 600°C. Each of the four heats exhibited a different stress-free swelling behavior at 400°C, with the creep rate following the swelling according to the familiar B{sub o} + DS creep law. No stress-free swelling was observed at the other three irradiation temperatures. Using a stress exponent of n = 1.0 as the defining criterion, {open_quotes}classic{close_quotes} irradiation creep was found at all temperatures, but, only over limited stress ranges that decreased with increasing temperature. The creep coefficient B{sub o} is a little lower (≈50%) than that observed for austenitic steel, but the swelling-creep coupling coefficient D is comparable to that of austenitic steels. Primary transient creep behavior was also observed at all temperatures except 400°C, and thermal creep behavior was found to dominate the deformation at high stress levels at 550 and 600°C.

Download or read book Variability of Irradiation Creep and Swelling of HT9 Irradiated to High Neutron Fluence at 400 600 C written by MB. Toloczko and published by . This book was released on 1999 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sets of pressurized tubes constructed from a combination of three lots of HT9 and two heat-treatments were examined after irradiation in FFTF-MOTA at four different temperatures between 400 and 600°C. Diametral measurements indicated that small amounts of swelling occurred at 400°C, with the magnitude of the swelling varying from tube-set to tube-set. At 495, 550, and 600°C, no indications of swelling were observed. Over a limited stress range that decreased with increasing irradiation temperature, the irradiation creep was found to be proportional to the stress level and mirrored the swelling behavior, confirming the Bo + DS creep model. The creep compliance, Bo, appears to be about half of that observed in austenitic steels, whereas the creep-swelling coupling coefficient, D, appears to be comparable to that of austenitics. At the highest stress levels examined, the value of the stress exponent became much greater than 1.0. Higher irradiation temperatures resulted in creep behavior with pronounced thermal creep characteristics. A primary creep transient was observed at the three higher irradiation temperatures and increased in magnitude with increasing irradiation temperature, while a stress exponent between 1.0 and 2.0 was observed at 550°C.

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 In reactor Deformation of Solution Annealed Type 304L Stainless Steel written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past six years at EBR-II, a great deal of information has been obtained on the in-reactor behavior of solution annealed-Type 304L stainless steel. This information consists of the following: (1) Irradiation induced swelling results in the form of immersion density and transmission electron microscopy (TEM) measurements on unstressed material that extend over a temperature range of 395 to 530°C and a neutron fluence range of 1.8 x 1022 to 9.3 x 1022 n/cm2 (E greater than 0.1 MeV). (2) Irradiation induced creep results from helium pressurized capsules irradiated at a temperature of 415°C. The hoop stress range covered in the experiment was 0 to 27.3 ksi, and the peak neutron fluence obtained to date is 7.6 x 1022 n/cm2 (E greater than 0.1 MeV). (3) Residual stress measurements (slit tube technique) with complementary TEM gradient studies on stressed and unstressed capsules. (4) Comparative swelling studies of stressed cladding material and unstressed capsule material from encapsulated EBR-II driver fuel experiments over wide ranges of temperature and neutron fluences.

Download or read book Fatigue Behavior and Microstructure of Neutron Irradiated Thin Section Type 304 Stainless Steel at Elevated Temperatures written by DJ. Michel and published by . This book was released on 1975 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of high fluence fast neutron irradiation on the fatigue behavior, microstructure, swelling, and microhardness were evaluated for annealed Type 304 stainless steel which had attained fluences near 1.6 x 1023 neutrons (n)/cm2 (> 0.1 MeV) at irradiation temperatures from 370 to 470°C (698 to 878°F). Unnotched fatigue specimens remotely prepared from the irradiated material were cycled at resonance in reverse bending in air at constant amplitude at 427 and 593°C (800 and 1100°F). At 427°C, the fatigue life was found to be strongly dependent on irradiation temperature. A decrease in fatigue life from 2 x 105 to 1.1 x 104 cycles was seen with increasing irradiation temperature within the range investigated. For irradiation temperatures below approximately 427°C, the fatigue life was found to decrease with increasing fluence in the range from 1.3 x 1022 to 1.5 x 1023 n/cm2 (> 0.1 MeV). The fatigue behavior of specimens tested at 593°C was characterized by a similar irradiation temperature dependency. At 593°C, however, little effect of fluence was observed in the irradiation temperature range below 427°C. At both test temperatures the nuclear exposure produced an increase in fatigue life at irradiation temperatures below 450°C.

Download or read book Irradiation Effects on the Microstructure on Properties of Metals written by ASTM International Symposium on Effects of Radiation on Structural Materials and published by ASTM International. This book was released on 1976 with total page 502 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Microstructure and Swelling of Fast Neutron Irradiated Type 304 Stainless Steel written by D. J. Michel and published by . This book was released on 1974 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of high-fluence, fast-neutron irradiation on the microstructure, swelling, and microhardness were evaluated for annealed Type 304 stainless steel that had attained fluences near 1.6 X 10 to the 23rd power n/sq cm> 0.1 MeV at irradiation temperatures from 370C to 470C (698F to 878F). Transmission electron microscopy was employed to characterize the radiation-induced void and defect structures. A maximum swelling of 10.4% was determined by immersion density measurements and independently confirmed from the microscopy data. Ambient temperature microhardness measurements were found to be in general agreement with calculated microhardness values based on the microscopy data. The calculations indicate that the radiation-induced voids were the primary microstructural component responsible for the measured microhardness. All results show the strong influence of the irradiation temperature and neutron fluence gradients experienced by the material during the EBR-II exposure.

Download or read book Metals Abstracts written by and published by . This book was released on 1974 with total page 998 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Creep of Annealed Type 304 Stainless Steel During Irradiation and Its Engineering Significance written by J. W. Carter and published by . This book was released on 1967 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annealed Type 304 stainless steel creep properties during neutron irradiation have been determined in the temperature range of 500 to 750 C and in the stress range of 10,000 to 30,000 psi. The minimum creep rates determined for creep during irradiation are essentially the same as those for unirradiated annealed Type 304 stainless steel. Creep rates are correlatable with the Arrhenius equation and the Larson-Miller parameter. Although little difference in creep rates was observed, significant reductions in creep-rupture time and creep-strain were observed. The data lend itself to parametric correlations of rupture time. In-reactor and ex-reactor creep-rupture strains are found to have different temperature dependence.

Download or read book Irradiation Creep of Austenitic Steels Irradiated Up to High Damage Dose written by VK. Shamardin and published by . This book was released on 2000 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The irradiation-induced creep and swelling of annealed 16Cr-15Ni-3Mo-Nb stainless steels with different contents of carbon and boron in BOR-60 at 420°C have been investigated to exposures of 100 dpa. Swelling depends on carbon content and boron. The creep rate directly depends on stress and instantaneous swelling rate. The creep-swelling oupling coefficient of austenitic steels does not appear to be very sensitive to microaddition.