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Experimental Assessments Of Notch Ductility And Tensile Strength Of Stainless Steel Weldments After 120c Neutron Irradiation
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Book Synopsis Experimental Assessments of Notch Ductility and Tensile Strength of Stainless Steel Weldments After 120°C Neutron Irradiation by : NG. Awadalla
Download or read book Experimental Assessments of Notch Ductility and Tensile Strength of Stainless Steel Weldments After 120°C Neutron Irradiation written by NG. Awadalla and published by . This book was released on 1987 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Charpy-V (Cv) properties of American Iron and Steel Institute (AISI) 300 series stainless steel plate, weld, and weld heat-affected zone (HAZ) materials from commercial production weldments in 406-mm-diameter pipe (12.7-mm wall) were investigated in unirradiated and irradiated conditions. Weld and HAZ tensile properties were also assessed in the two conditions. The plates and weld filler wires represent different steel melts; the welds were produced using the multipass metal inert gas (MIG) process. Weldment properties in two test orientations were evaluated. Specimens were irradiated in a light water cooled and moderated reactor to 1 x 1020 n/cm2, E > 0.1 MeV, using a controlled temperature assembly. Specimen tests were performed at 25 and 125°C.
Book Synopsis Initial Assessments of Notch Ductility Behavior of A533 Pressure Vessel Steel with Neutron Irradiation by :
Download or read book Initial Assessments of Notch Ductility Behavior of A533 Pressure Vessel Steel with Neutron Irradiation written by and published by . This book was released on 1968 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Exploratory assessments were made of the Charpy-V notch ductility characteristics of heavy section A533-B and A533-C steel plate and submerged arc weldments following neutron irradiation at 550F. The experimental evaluations were performed largely with commercial production materials and included comparisons of materials in both Class 1 and Class 2 strength ranges. Postirradiation notch ductility properties of one 5-3/4-in. A533-B Class 1 electroslag weldment were also developed. Assessments made of relative irradiation performance were assisted by a compilation of recent information on the response of the ASTM reference A302-B steel plate. Major research findings include the observation of significant variability in radiation embrittlement sensitivity of A533-B and A533-C steel wherein the sensitivity level of plate and weld metal in some cases exceeded that of the ASTM reference plate. High radiation embrittlement sensitivity was noted for both submerged arc weld deposits examined; however, the data suggest that the performance of the weld-heat-affected zone parallels that of the parent plate. High embrittlement sensitivity was also noted for the electroslag weld deposit, in contrast to markedly low sensitivity of the weldment parent plate. The notch ductility behavior of A533 plate and weld metal under 550F irradiation was not found to be measurably influenced by either the strength class (Class 1 or 2) or by the particular grade of steel (Grade B or C). Similarly, there were no marked variations in irradiation response through the thickness of plate or weld metals, or between RW (longitudinal) versus WR (Transverse) orientations in cross-rolled plate. (Author).
Book Synopsis Mechanical Properties of Irradiated Welds in Stainless Steel by : J. Walter Joseph
Download or read book Mechanical Properties of Irradiated Welds in Stainless Steel written by J. Walter Joseph and published by . This book was released on 1960 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Initial Assessments of Notch Ductility Behavior of A533 Pressure Vessel Steel with Neutron Irradiation by : J. Russell Hawthorne
Download or read book Initial Assessments of Notch Ductility Behavior of A533 Pressure Vessel Steel with Neutron Irradiation written by J. Russell Hawthorne and published by . This book was released on 1968 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: Exploratory assessments were made of the Charpy-V notch ductility characteristics of heavy section A533-B and A533-C steel plate and submerged arc weldments following neutron irradiation at 550F. The experimental evaluations were performed largely with commercial production materials and included comparisons of materials in both Class 1 and Class 2 strength ranges. Postirradiation notch ductility properties of one 5-3/4-in. A533-B Class 1 electroslag weldment were also developed. Assessments made of relative irradiation performance were assisted by a compilation of recent information on the response of the ASTM reference A302-B steel plate. Major research findings include the observation of significant variability in radiation embrittlement sensitivity of A533-B and A533-C steel wherein the sensitivity level of plate and weld metal in some cases exceeded that of the ASTM reference plate. High radiation embrittlement sensitivity was noted for both submerged arc weld deposits examined; however, the data suggest that the performance of the weld-heat-affected zone parallels that of the parent plate. High embrittlement sensitivity was also noted for the electroslag weld deposit, in contrast to markedly low sensitivity of the weldment parent plate. The notch ductility behavior of A533 plate and weld metal under 550F irradiation was not found to be measurably influenced by either the strength class (Class 1 or 2) or by the particular grade of steel (Grade B or C). Similarly, there were no marked variations in irradiation response through the thickness of plate or weld metals, or between RW (longitudinal) versus WR (Transverse) orientations in cross-rolled plate. (Author).
Book Synopsis Stress Relaxation in Stainless Steel During Irradiation by : J. Walter Joseph
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 Synopsis Charpy-v Notch Ductility Characteristics of Neutron-irradiated A537-b and A350-lf2 Steel Weldments by : Robert A Gray (Jr)
Download or read book Charpy-v Notch Ductility Characteristics of Neutron-irradiated A537-b and A350-lf2 Steel Weldments written by Robert A Gray (Jr) and published by . This book was released on 1970 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The nuclear service performance of thin (3/4-inch) structural steel plate irradiated at 150F (65C) to a fluence of 2.5 x 10 to the 18th power neutrons sq cm of energies greater than 1 MeV has been examined and documented with experimental results. Five 3/4-inch A537-B steel plates, an A350-LF2 forging, and weldments of both types of steel provided the specimen stock for the irradiation assessments. The two steels responded to low-temperature irradiation in a manner similar to a well-documented A212-B pressure vessel steel. However, both A537-B and A350-LF2 steels have an inherently greater tolerance to the effects of irradiation damage by virtue of their lower initial transition temperature. Embrittlement due to irradiation produced increases in transition temperature, but for no component of the weldments studied was the 30-ft-lb value greater than 65F (18C). The postirradiation assessments of the Charpy-V notch shelf energy values of A537-B plate in the ASTM WR orientation (weak direction) revealed a marked reduction in the steel's fracture resistance at maximum (shelf-level) ductility. This is believed to be due to the high cross-rolling ratio and points up the need to maintain ratios near unity to insure WR notch ductility properties approximating those for the RW (strong) direction. (Author).
Book Synopsis Experimental Investigation of Multicycle Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits by : Hawthorne, JR.
Download or read book Experimental Investigation of Multicycle Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits written by Hawthorne, JR. and published by . This book was released on 1981 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Postirradiation heat treatment (annealing) at 399°C has demonstrated a capability for the relief of radiation embrittlement to reactor vessel steels. Building on an earlier investigation, this report describes a study of Charpy-V (CV) notch ductility and tensile properties behavior of two representative reactor vessel welds under cyclic 399°C postirradiation annealing and 288°C reirradiation. The welds were by the submerged-arc process and were chosen for their high radiation sensitivity (high copper content) and for their difference in as-fabricated CV upper-shelf energy levels derived from different welding fluxes. Weld properties were determined at each phase of the anneal-reirradiation-reanneal-reirradiation sequence.
Book Synopsis Effects of Fast Neutron Irradiation on the Fracture Behavior of Stainless Steel by : FH. Huang
Download or read book Effects of Fast Neutron Irradiation on the Fracture Behavior of Stainless Steel written by FH. Huang and published by . This book was released on 1982 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: Tensile tests were performed on notched and unnotched 20 percent cold worked Type 316 stainless steel specimens sectioned from EBR-II duct thimbles. The test results show that the notch sensitivity of irradiated specimens is slightly temperature and neutron fluence dependent and that the material is notch weakened at 600°C. A transition was observed from notch strengthening at low fluences to notch weakening for specimens irradiated to fluences greater than 4 x 1022 n/cm2 (E >0.1 MeV). In addition, the results of the notch tensile tests were used to estimate the ductile fracture toughness of 20 percent cold worked Type 316 stainless steel duct irradiated to a fluence of 7.8 x 1022 n/cm2 (E >0.1 MeV). The influence of irradiation temperature on the strength and ductility of notched specimens is also discussed.
Book Synopsis Tensile Properties of Fast Reactor Irradiated Type 304 Stainless Steel by : RL. Fish
Download or read book Tensile Properties of Fast Reactor Irradiated Type 304 Stainless Steel written by RL. Fish and published by . This book was released on 1976 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Tension tests were performed on annealed Type 304 stainless steel specimens sectioned from Experimental Breeder Reactor-II (EBR-II) duct thimbles. The specimens had accumulated neutron fluences of up to 10.3 x 1022 neutrons (n)/cm2, E > 0.1 MeV (10.3 x 1026 n/m2, E x16 fJ). Irradiation temperatures for the material tested ranged from 700 to 750°F (644 to 672 K). The tests were performed at temperatures of room temperature to 1400°F (1033 K), employing strain rates of 2 x 10-3 to 2/min (3.3 x 10-5 to 3.3 x 10-2/s).
Book Synopsis Mechanical Properties of 1950's Vintage Type 304 Stainless Steel Weldment Components After Low Temperature Neutron Irradiation by : RL. Sindelar
Download or read book Mechanical Properties of 1950's Vintage Type 304 Stainless Steel Weldment Components After Low Temperature Neutron Irradiation written by RL. Sindelar and published by . This book was released on 1994 with total page 33 pages. Available in PDF, EPUB and Kindle. Book excerpt: The reactor vessels of the nuclear production reactors at the Savannah River Site (SRS) were constructed in the 1950's from Type 304 stainless steel plates welded with Type 308 stainless steel filler using a multipass metal-inert-gas process. A mechanical properties database for irradiated material has been developed for the vessel with materials from archival primary coolant system piping irradiated at low temperatures (75 to 150°C) in the State University of New York at Buffalo reactor (UBR) and the High Flux Isotope Reactor (HFIR) to doses of 0.065 to 2.1 dpa. Fracture toughness, tensile, and Charpy-V impact properties of the weldment components (base, weld, and weld heat-affected-zone (HAZ)) have been measured at temperatures of 25°C and 125°C in the L-C and C-L orientations for materials in both the irradiated and unirradiated conditions for companion specimens. Fracture toughness and tensile properties of specimens cut from an SRS reactor vessel sidewall with doses of 0.1 and 0.5 dpa were also measured at temperatures of 25 and 125°C. The irradiated materials exhibit hardening with loss of work hardenability and a reduction in toughness relative to the unirradiated materials with a slight sensitivity to exposure. Irradiation increased the yield strength between 22% to 187% with a concomitant tensile strength increase between-9% to 29%. The irradiation-induced decrease in the elastic-plastic fracture toughness (JD at 1 mm crack extension) is between 26% to 64%; the range of JICvalues are 72.8 to 366 kJ/m2 for the irradiated materials. Similarly, Charpy V-notch results show a 38% to 59% decrease in impact absorbed energies. The C-L orientation shows significantly lower absorbed energies and fracture toughness parameters than the L-C orientation for both the base and HAZ components in both the unirradiated and irradiated conditions.
Book Synopsis Effect of Neutron Irradiation on Mechanical Properties of AISI Type 347 Stainless Steel by : M. Kangilaski
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.
Book Synopsis Mechanical Properties of 1950's Vintage 304 Stainless Steel Weldment Components After Low Temperature Neutron Irradiation by :
Download or read book Mechanical Properties of 1950's Vintage 304 Stainless Steel Weldment Components After Low Temperature Neutron Irradiation written by and published by . This book was released on 1991 with total page 53 pages. Available in PDF, EPUB and Kindle. Book excerpt: The reactor vessels of the nuclear production reactors at the Savannah River Site (SRS) were constructed in the 1950's from Type 304 stainless steel plates welded with Type 308 stainless steel filler using the multipass metal inert gas process. An irradiated mechanical properties database has been developed for the vessel with materials from archival primary coolant system piping irradiated at low temperatures (75 to 150°C) in the State University of New York at Buffalo reactor (UBR) and the High Flux Isotope Reactor (HFIR) to doses of 0.065 to 2.1 dpa. Fracture toughness, tensile, and Charpy-V impact properties of the weldment components (base, weld, and weld heat-affected-zone (HAZ)) have been measured at temperatures of 25°C and 125°C in the L-C and C-L orientations for materials in both the irradiated and unirradiated conditions for companion specimens. Fracture toughness and tensile properties of specimens cut from an SRS reactor vessel sidewall with doses of 0.1 and 0.5 dpa were also measured at temperatures of 25 and 125°C. The irradiated materials exhibit hardening with loss of work hardenability and a reduction in toughness relative to the unirradiated materials. The HFIR-irradiated materials show an increase in yield strength between about 20% and 190% with a concomitant tensile strength increase between about 15% to 30%. The elastic-plastic fracture toughness parameters and Charpy-V energy absorption both decrease and show only a slight sensitivity to dose. The irradiation-induced decrease in the elastic-plastic fracture toughness (J{sub def} at 1 mm crack extension) is between 20% to 65%; the range of J{sub 1C} values are 72.8 to 366 kJ/m2 for the irradiated materials. Similarly, Charpy V-notch results show a 40% to 60% decrease in impact energies.
Book Synopsis BEHAVIOR OF MECHANICAL PROPERTIES IN NEUTRON IRRADIATED 12Ni-5Cr-3Mo MARAGING STEEL PLATE AND COMPANION WELD METALS. by : R. A Gray (Jr)
Download or read book BEHAVIOR OF MECHANICAL PROPERTIES IN NEUTRON IRRADIATED 12Ni-5Cr-3Mo MARAGING STEEL PLATE AND COMPANION WELD METALS. written by R. A Gray (Jr) and published by . This book was released on 1969 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Changes of Charpy-V-notch ductility and tensile strength in neutron-irradiated 12Ni-5Cr-3Mo maraging steel have been evaluated following low (less than 250F) and elevated (550 to 740F) temperature exposure. The study was performed with six heats of 1-in.-thick plate material aged at 900F for 2 and 20 hr to nominal yield strengths of 160 and 180 ksi, respectively. The long-term thermal stability of both heat-treatment conditions was investigated for the conditions of irradiation. The less than 250F and 550F irradiation performance of matching (15-5-3) and mismatching (17Ni-2Co-3Mo) TIG weld deposits maraged to 180 ksi yield strength was also assessed in this study. Changes in the general properties of the 12-5-3 maraging steel plate and companion weld metals were found to be rather small with less than 250F exposures, indicating good resistance to neutron-induced embrittlement. However, a marked deterioration of notch-ductility properties with long-term exposure at elevated temperature was revealed and traced to a nonnuclear thermal instability. The observed instability is believed to be a continuation of aging processes at temperatures well below the initial maraging temperature. Extended time-at-temperature treatments indicate that service above 550F may produce sufficient changes in properties for failure by low-energy tear. Aging treatments of 1900 to 3300 hours' duration increased the yield and tensile strengths of the 12-5-3 alloy by as much as 52.0 and 53.3 ksi, respectively, while not altering appreciably the percentage of elongation and the reduction in area. (Author).
Book Synopsis Evaluation of Discontinuities in a Stainless Steel Weldment with Radiographic and Ultrasonic Techniques by : F. J. Lambert
Download or read book Evaluation of Discontinuities in a Stainless Steel Weldment with Radiographic and Ultrasonic Techniques written by F. J. Lambert and published by . This book was released on 1959 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Swelling and Tensile Property Changes in Neutron-Irradiated Type 316 Stainless Steel by : KR. Garr
Download or read book Swelling and Tensile Property Changes in Neutron-Irradiated Type 316 Stainless Steel written by KR. Garr and published by . This book was released on 1976 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: Specimens of Type 316 stainless steel, given different thermomechanical treatments resulting in either a cold-worked or solution-annealed and aged structure, were irradiated in the Experimental Breeder Reactor-II (EBR-II) at 500 to 600 °C (932 to 1112°F) to a fluence of 7.4 x 1026 neutrons (n)/m2 (E > 0.1 MeV). Three specimen configurations were used: small sheet tension specimens, small right-circular cylinders for immersion density, and thin foils for transmission electron microscopy (TEM). TEM revealed voids in all specimens. Immersion density indicated swelling in cold-rolled specimens only after irradiation at temperatures near 600°C (1112°F). Considerable recovery and precipitation were observed in the cold-rolled specimens. Results of tension tests revealed an increase in strength and decrease in ductility for specimens originally in a solution-annealed and aged condition. Cold-rolled specimens exhibited a decrease in strength and a slight increase in total elongation. True stress-true plastic strain was best described by the Ludwigson equation, ? = K3?n3 ± exp (K4 + n4?), in all cases. Irradiation causes a decrease in the work-hardening exponent, n3, and strength factor, K3. After irradiation, the values of n3 and K3 tended toward common values for both preirradiation treatments.
Book Synopsis Orientation Dependency of Mechanical Properties of 1950's Vintage Type 304 Stainless Steel Weldment Components Before and After Low Temperature Neutron Irradiation by :
Download or read book Orientation Dependency of Mechanical Properties of 1950's Vintage Type 304 Stainless Steel Weldment Components Before and After Low Temperature Neutron Irradiation written by and published by . This book was released on 1992 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Databases of mechanical properties for both the piping and reactor vessels at the Savannah River Site (SRS) were developed from weldment components (base, weld, and weld heat-affected-zone (HAZ)) of archival piping specimens in the unirradiated and irradiated conditions. Tensile, Charpy V-notch (CVN), and Compact Tension C(T) specimens were tested at 25 and 125C before and after irradiation at low temperatures (90 to 150C) to levels of 0.065 to 2.1 dpa. irradiation hardened the weldment components and reduced the absorbed energy and toughness properties from the unirradiated values. A marked difference in the Charpy V-notch absorbed energy and the elastic-plastic fracture toughness (J{sub IC}) was observed for both the base and HAZ components with the C-L orientation being lower in toughness than the L-C orientation in both the unirradiated and irradiated conditions. Fracture surface examination of the base and HAZ components of unirradiated C(T) specimens showed a ''channel'' morphology in the fracture surfaces of the C-L specimens, whereas equiaxed ductile rupture occurred in the L-C specimens. Chromium carbide precipitation in the HAZ component reduced the fracture toughness of the C-L and L-C specimens compared to the respective base component C-L and L-C specimens. Optical metallography of the piping materials showed stringers of second phase particles parallel to the rolling direction along with a banding or modulation in the microchemistry perpendicular to the pipe axis or rolling direction of the plate material.
Book Synopsis Effect of Decarburization on Notch Sensitivity and Fatigue-crack-propagation Rates in 12 MoV Stainless-steel Sheet by : William H. Herrnstein
Download or read book Effect of Decarburization on Notch Sensitivity and Fatigue-crack-propagation Rates in 12 MoV Stainless-steel Sheet written by William H. Herrnstein and published by . This book was released on 1961 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: "Tests were conducted in order to determine the effect of surface decarburization on the notch-sensitivity and rate of fatigue crack propagation in 12 Mov stainless-steel sheet at room temperature. Three specimen configurations were utilized in the course of the investigation: standard tensile specimen, 9-inch-wide specimens containing fatigue cracks or thread-cut notches of 0.005-inch radius, and 2-inch-wide specimens containing fatigue cracks. The 12 Mov stainless-steel sheet in the normal condition was found to have an ultimate tensile strength of 251 ksi and to be extremely notch sensitive. The material in the decarburized condition was found to have an ultimate strength of 210 ksi and to be considerably stronger than the normal material in the presence of fatigue cracks. Decarburization did not appear to have any siinfluence incluence on the rate of fatigue crack propagation in the 2-inch-wide specimens at the stress levels considered. In addition to the tests, two methods for predicting residual static strength and their application to the material are discussed."--Summary.
