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in creator/contributor: "Haggag, F.M."  
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Degradation of mechanical properties of stainless steel cladding due to neutron irradiation and thermal aging

Description: Thermal aging of three-wire series-arc stainless steel weld overlay cladding at 288{degrees}C for 1605 h resulted in an appreciable decrease (16%) in the Charpy V-notch (CVN) upper-shelf energy (USE), but the effect on the 41-J transition temperature shift was very small (3{degrees}C). The combined effect following neutron irradiation at 288{degrees}C to a fluence of 5 X 10{sup 19} neutrons/cm{sup 2} (>1 MeV) was a 22% reduction in the USE and a 29{degrees}C shift in the 41-J transition tempera… more
Date: September 1, 1994
Creator: Haggag, F. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Results of irradiated cladding tests and clad plate experiments

Description: Two aspects critical to the fracture behavior of three-wire stainless steel cladding were investigated by the Heavy-Section Steel Technology (HSST) Program: (1) radiation effects on cladding strength and toughness, and (2) the response of mechanically loaded, flawed structures in the presence of cladding (clad plate experiments). Postirradiation testing results show that, in the test temperature range from /minus/125 to 288/degree/C, the yield strength increased, and ductility insignificantly i… more
Date: January 1, 1988
Creator: Haggag, F.M. & Iskander, S.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effects of thermal aging and neutron irradiation on the mechanical properties of three-wire stainless steel weld overlay cladding

Description: Thermal aging of three-wire series-arc stainless steel weld overlay cladding at 288{degrees}C for 1605 h resulted in an appreciable decrease (16%) in the Charpy V-notch (CVN) upper-shelf energy (USE), but the effect on the 41-J transition temperature shift was very small (3{degrees}C). The combined effect of aging and neutron irradiation at 288{degrees}C to a fluence of 5 x 10{sup 19} neutrons/cm{sup 2} (> 1 MeV) was a 22% reduction in the USE and a 29{degrees}C shift in the 41-J transition tem… more
Date: May 1, 1997
Creator: Haggag, F.M. & Nanstad, R.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of irradiation on strength and toughness of commercial LWR vessel cladding

Description: The potential for stainless steel cladding to improve the fracture behavior of an operating nuclear reactor pressure vessel, particularly during certain overcooling transients, may depend greatly on the properties of the irradiated cladding. Therefore, weld overlay cladding irradiated at temperatures and to fluences relevant to power reactor operation was examined. The cladding was applied to a pressure vessel steel plate by the three-wire series-arc commercial method. Cladding was applied in t… more
Date: January 1, 1987
Creator: Haggag, F.M.; Corwin, W.R.; Alexander, D.J. & Nanstad, R.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Use of miniature and standard specimens to evaluate effects of irradiation temperature on pressure vessel steels

Description: The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-cooled reactor (MHTGR) are being investigated, primarily because the operating temperatures are low (121 to 210{degrees}C (250--410{degrees}F)) compared to those for commercial light-water reactors (LWRs) ({approximately}288{degrees}C (550{degrees}F)). The need for design data on the reference temperature shift necessitated the irradiation at different temperatures of A 533 grade B class 1 plate.… more
Date: January 1, 1991
Creator: Haggag, F.M.; Nanstad, R.K. (Oak Ridge National Lab., TN (United States)) & Byrne, S.T. (ABB/Combustion Engineering, Inc., Windsor, CT (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The use of field indentation microprobe in measuring mechanical properties of welds

Description: A field indentation microprobe (FIM) was conceived for evaluating the structural integrity of metallic components (including base metal, welds, and heat-affected zones) in situ in a nondestructive manner. The FIM consists of an automated ball indentation (ABI) unit for determining the mechanical properties (yield strength, flow properties, estimates of fracture toughness, etc.) and a nondestructive evaluation (NDE) unit (consisting of ultrasonic transducers and a video camera) for determining t… more
Date: January 1, 1989
Creator: Haggag, F.M.; Wong, H.; Alexander, D.J. & Nanstad, R.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Heavy-Section Steel Irradiation Program on irradiation effects in light-water reactor pressure vessel materials

Description: The safety of commercial light-water nuclear plants is highly dependent on the structural integrity of the reactor pressure vessel (RPV). In the absence of radiation damage to the RPV, fracture of the vessel is difficult to postulate. Exposure to high energy neutrons can result in embrittlement of radiation-sensitive RPV materials. The Heavy-Section Steel Irradiation (HSSI) Program at Oak Ridge National Laboratory, sponsored by the US Nuclear Regulatory Commission (USNRC), is assessing the effe… more
Date: July 1, 1995
Creator: Nanstad, R. K.; Corwin, W. R.; Alexander, D. J.; Haggag, F. M.; Iskander, S. K.; McCabe, D. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation effects on fracture toughness of two high-copper submerged-arc welds, HSSI Series 5. Volume 1, Main report and Appendices A, B, C, and D

Description: The Fifth Irradiation Series in the Heavy-Section Steel Irradiation Program obtained a statistically significant fracture toughness data base on two high-copper (0.23 and 0.31 wt %) submerged-arc welds to determine the shift and shape of the K{sub Ic} curve as a consequence of irradiation. Compact specimens with thicknesses to 101.6 mm (4 in) in the irradiated condition and 203.2 mm (8 in) in the unirradiated condition were tested, in addition to Charpy impact, tensile, and drop-weight specimen… more
Date: October 1, 1992
Creator: Nanstad, R. K.; Haggag, F. M.; McCabe, D. E.; Iskander, S. K.; Bowman, K. O. & Menke, B. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation effects on fracture toughness of two high-copper submerged-arc welds, HSSI series 5. Volume 2, Appendices E and F

Description: The Fifth Irradiation Series in the Heavy-Section Steel irradiation (HSSI) Program was aimed at obtaining a statistically significant fracture toughness data base on two weldments with high-copper contents to determine the shift and shape of the K{sub lc} curve as a consequence of irradiation. The program included irradiated Charpy V-notch impact, tensile, and drop-weight specimens in addition to compact fracture toughness specimens. Compact specimens with thicknesses of 25.4, 50.8, and 101.6 m… more
Date: October 1, 1992
Creator: Nanstad, R. K.; Haggag, F. M.; McCabe, D. E.; Iskander, S. K.; Bowman, K. O. & Menke, B. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Statistical analyses of fracture toughness results for two irradiated high-copper welds

Description: The objectives of the Heavy-Section Steel Irradiation Program Fifth Irradiation Series were to determine the effects of neutron irradiation on the transition temperature shift and the shape of the K{sub Ic} curve described in Sect. 6 of the ASME Boiler and Pressure Vessel Code. Two submerged-arc welds with copper contents of 0.23 and 0.31% were commercially fabricated in 215-mm-thick plates. Charpy V-notch (CVN) impact, tensile, drop-weight, and compact specimens up to 203.2 mm thick (1T, 2T, 4… more
Date: January 1, 1990
Creator: Nanstad, R. K.; McCabe, D. E.; Haggag, F. M.; Bowman, K. O. & Downing, D. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effects of irradiation on K/sub Ic/ curves for high-copper welds

Description: The Fifth Irradiation Series in the Heavy-Section Steel Technology (HSST) Program is aimed at obtaining a statistically significant fracture toughness data base on two weldments with high-copper contents to determine the shift and shape of the K/sub Ic/ curve as a consequence of irradiation. The program includes irradiated Charpy V-notch impact, tensile, and drop-weight specimens in addition to compact fracture toughness specimens. Compact specimens (CS) with thicknesses of 25.4, 50.8, and 101.… more
Date: January 1, 1988
Creator: Nanstad, R. K.; McCabe, D. E.; Menke, B. H.; Iskander, S. K. & Haggag, F. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Radiation-induced temperature shift of thhe ASME K/sub Ic/ curve

Description: The objective of this study was to determine the effects of neutron irradiation on the temperature shift and shape of the K/sub Ic/ curve described in Sect. XI of the ASME Boiler and pressure Vessel Code. Two submerged-arc welds with copper contents of 0.23 and 0.31 wt % were commercially fabricated in 215-mm-thick plate. Charpy impact, tensile, dropweight, and compact specimens up to 203.2 mm thick were fabricated and tested to provide a large data for unirradiated material. Similar specimens … more
Date: January 1, 1989
Creator: Nanstad, R.K.; Haggag, F.M. & Iskander, S.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effects of irradiation on initiation and crack-arrest toughness of two high-copper welds and on stainless steel cladding

Description: The objective of the study on the high-copper welds is to determine the effect of neutron irradiation on the shift and shape of the ASME K{sub Ic} and K{sub Ia} toughness curves. Two submerged-arc welds with copper contents of 0.23 and 0.31 wt % were commercially fabricated in 220-mm-thick plate. Compact specimens fabricated from these welds were irradiated at a nominal temperature of 288{degree}C to fluences from 1.5 to 1.9 {times} 10{sup 19} neutrons/cm{sup 2} (>1 MeV). The fracture toughness… more
Date: January 1, 1990
Creator: Nanstad, R.K.; Iskander, S.K. & Haggag, F.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Materials property testing using a stress-strain microprobe

Description: The Stress-Strain Microprobe (SSM) uses an automated ball indentation technique to obtain flow data from a localized region of a test specimen or component. This technique is used to rapidly determine the yield strength and microstructural condition of a variety of materials including pressure vessel steels, stainless steels, and nickel-base alloys. The SSM provides an essentially non-destructive technique for the measurement of yield strength data. This technique is especially suitable for the… more
Date: September 1, 1998
Creator: Panayotou, N.F.; Baldrey, D.G. & Haggag, F.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aging management of major LWR components with nondestructive evaluation

Description: Nondestructive evaluation of material damage can contribute to continued safe, reliable, and economical operation of nuclear power plants through their current and renewed license period. The aging mechanisms active in the major light water reactor components are radiation embrittlement, thermal aging, stress corrosion cracking, flow-accelerated corrosion, and fatigue, which reduce fracture toughness, structural strength, or fatigue resistance of the components and challenge structural integrit… more
Date: December 31, 1997
Creator: Shah, V. N.; MacDonald, P. E.; Akers, D. W.; Sellers, C.; Murty, K. L.; Miraglia, P. Q. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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