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Structural analysis of a reflux pool-boiler solar receiver

Description: Coupled thermal-structural finite element calculations of a reflux pool-boiler solar receiver were performed to characterize the operating stresses and to address issues affecting the service life of the receiver. Analyses performed using shell elements provided information for receiver material selection and design optimization. Calculations based on linear elastic fracture mechanics principles were performed using continuum elements to assess the vulnerability of a seam-weld to fatigue crack … more
Date: June 1, 1991
Creator: Hoffman, E. L. & Stone, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility study of acoustic emission monitoring of pinch welding tritium reservoir fill stems at the Savannah River Site

Description: A study was conducted to determine whether acoustic emission monitoring would be feasible in monitoring the solid-state resistance pinch weld used to seal tritium reservoirs at the Savannah River Site. Experiments were performed using a commercially available acoustic emission detection system, with a transducer mounted on a flat milled onto one of the pinch weld electrodes. Welds were made using a wide range of weld power, from very cold, with no metallurgical bond, to hot, with local fusion a… more
Date: January 1, 1990
Creator: Clark, E.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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304L stainless steel resistance to cesium chloride

Description: B and W Hanford Company have two Oak Ridge National Laboratory (ORNL) Type 4 canisters filled with cesium chloride (CsCl) originally produced at WESF (Waste Encapsulation and Storage Facility). These canisters are constructed of 304L stainless steel per drawing ORNL 970-294. Instead of removing the CsCl from the Type 4 canisters and repacking into an Inner Capsule, it is intended (for ALARA, schedule and cost purposes) that the Type 4 canisters be decontaminated (scrubbed) and placed [whole] in… more
Date: August 27, 1998
Creator: Graves, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The effects of tritium and decay helium on the fracture toughness properties of stainless steels

Description: J-integral fracture mechanics techniques and scanning electron microscopy observations were used to investigate the effects of tritium and its decay product, helium-3, on Types 304L, 316L, 21-6-9, A286, and JBK-75 (Modified A286) stainless steels. Tritium-exposed samples of each steel had lower fracture toughness values and less resistance to stable crack growth than control samples. Type 316L stainless steel was more resistant to the embrittling effects of tritium and decay helium than the oth… more
Date: December 31, 1991
Creator: Morgan, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Aerosol filtration with steel fiber filters

Description: We have conducted an experimental study of aerosol penetration through a new high efficiency steel fiber filter and filter media that we developed in cooperation with Pall Corporation. Our previous studies have shown that sintered steel fiber media have significant improvements in higher filter efficiency and lower pressure drop than the previous steel filter technology based on sintered powder metal media. In the present study, we have measured the penetration of dioctyl sebacate (DOS) aerosol… more
Date: April 1, 1993
Creator: Bergman, W.; Wilson, K.; Larsen, G. & Lopez, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reactor safety research section probability of heat exchanger leaks

Description: Three heat exchangers (HXs) were changed out after the December 1991 leak of Process Water to the Savannah River. This leaves 6 of the original 304 stainless steel heat exchangers which will remain in K-Reactor for restart. This report discusses SRS site specific data which were used to estimate the probability of a leak within a one-year period as a function of leak rate and root cause in these six heat exchangers in conjunction with six new heat exchangers presently in service in K-Reactor. B… more
Date: February 1, 1992
Creator: Cramer, D. S.; Shine, E. P. & Copeland, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Rapid heating tensile tests of high-energy-rate-forged 316L stainless steel containing internal helium from radioactive decay of absorbed tritium

Description: 316L stainless steel is a candidate material for construction of equipment that will be exposed to tritium. This austenitic stainless steel is frequently used in the high-energy-rate-forged (HERF) metallurgical condition to take advantage of increased strength produced by cold work introduced by this process. Proper design of tritium-handling equipment will require an understanding of how helium-3, the product of radioactive decay of tritium, affects mechanical properties. This report describes… more
Date: December 31, 1990
Creator: Mosley, W. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Tritium and decay helium effects on the fracture toughness properties of types 316L, 304L and 21Cr-6Ni-9Mn stainless steels

Description: J-integral fracture mechanics techniques and electron microscopy observations were used to investigate the effects of tritium and its radioactive decay product, {sup 3}He, on Types 316L, 304L and 21Cr-6Ni-9Mn stainless steels. Tritium-exposed-and-aged steels had lower fracture-toughness values and shallower sloped crack-growth-resistance curves than unexposed steels. Both fracture-toughness parameters decreased with increasing concentrations of {sup 3}He. The fracture-toughness reductions were … more
Date: October 1, 1994
Creator: Morgan, M. J. & Tosten, M. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Long term laboratory corrosion monitoring of calcine bin set materials exposed to zirconia calcine

Description: Corrosion testing of Type 1025 carbon steel, 405, 304, 304L, 316L, and 347 stainless steels, and 6061-T6 aluminum were conducted in synthetic zirconia calcine to model long term corrosion performance of bin set material. Testing was conducted over a period of 17 years. The existing calcine bin set {number_sign}1 is constructed of Type 405 stainless steel, 2 through 4 are constructed of Type 304 stainless steel and 5 through 7 are constructed of Type 304L stainless steel. The highest rate observ… more
Date: June 1, 1994
Creator: Dirk, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Rapid heating tensile tests of high-energy-rate-forged 316L stainless steel containing internal helium from radioactive decay of absorbed tritium

Description: 316L stainless steel is a candidate material for construction of equipment that will be exposed to tritium. This austenitic stainless steel is frequently used in the high-energy-rate-forged (HERF) metallurgical condition to take advantage of increased strength produced by cold work introduced by this process. Proper design of tritium-handling equipment will require an understanding of how helium-3, the product of radioactive decay of tritium, affects mechanical properties. This report describes… more
Date: January 1, 1990
Creator: Mosley, W. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Dissolution of a 316L stainless steel vessel by a pool of molten aluminum

Description: Two experiments to study the dissolution of a torospherical stainless steel vessel by an isothermal pool of molten aluminum have been performed. The test vessels consisted of 24 inch diameter 316L stainless steel ``ASME Flanged and Dished Heads.`` The nominal values of the average melt temperatures for the two tests were: 977{degree}C and 1007{degree}C. The measurements of the dissolution depth as a function of the position along the vessel surface showed the dissolution to be spatially highly … more
Date: January 1, 1993
Creator: Tutu, N. K.; Finfrock, C. C.; Lara, J. D.; Schwarz, C. E. & Greene, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Robotic weld overlay coatings for erosion control. Quarterly progress report, October 1993--December 1993

Description: Research is being conducted to develop criteria for selecting weld overlay coatings for erosion mitigation in Circulated Fluidized Beds. Twelve weld overlay alloys were deposited on 1018 steel substrates using plasma arc welding. Ten samples from each coating were prepared for erosion testing. All selected coatings were erosion tested at 400C and their erosion resistance and microstructure evaluated. Steady state erosion rates were similar for several weld overlay coatings (Ultimet, Inconel-625… more
Date: January 20, 1994
Creator: Levin, B. F.; DuPont, J. N. & Marder, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reducing inadvertent alloying of metal/ceramic brazes

Description: Inadvertent alloying of Cu braze metal can compromise metal/ceramic seals. Electron microprobe analyses have quantified alloying of Cu brazes in metal/ceramic feedthroughs. Pin material and processing parameters above 1084C both affect alloying levels. Using either Kovar or Ni-plated 316L stainless steel pins limits alloying compared to Palco pins. Minimizing the time during which the braze is molten also avoids excessive alloying. The original thickness of the Ni plating on the Mo-Mn metalliza… more
Date: December 31, 1992
Creator: Stephens, J. J. & Hlava, P. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Robotic weld overlay coatings for erosion control. Quarterly technical progress report, January 1995--March 1995

Description: Research is presently being conducted to develop a criteria for selecting weld overlay coatings for erosion mitigation in Circulated Fluidized Beds. During the last two quarters tensile tests were performed at 400{degrees}C for the Ultimet, Inconel-625, 316L SS, C-22, and Stellite-6 wrought alloys. Also, the erosion tests for these materials at 400{degrees}C were completed. The results of mechanical and erosion tests are used to correlate mechanical properties of selected wrought alloys such as… more
Date: April 25, 1995
Creator: Levin, B. F.; Dupont, J. N. & Marder, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technology Base Studies of Long-Term MCFC Performance

Description: Cathode dissolution into the electrolyte matrix and endurance of current collector/separator plate materials are the main life-limiting factors of the state-of-the art MCFC. These components are also major contributors to the total system cost. Therefore, to reduce capital cost, it is necessary to minimize hardware corrosion and increase cell life. This study consists of experimental evaluation of corrosion processes with the objective to further practical; understanding of corrosion behavior o… more
Date: December 1, 1995
Creator: Selman, J.R. & Yazici, M.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Crack growth behavior of candidate waste container materials in simulated underground water

Description: Fracture-mechanics crack growth tests were conducted on 25.4-mm-thick compact tension specimens of Types 304L and 316L Stainless steel and Incoloy 825 at 93{degrees}C and 1 atmosphere of pressure in simulated J-13 well water, which is representative of the groundwater at the Yucca Mountain site in Nevada that is proposed for a high-level nuclear waste repository. Crack growth rates were measured under various load conditions: load ratios of 0.2--1.0, frequencies of 2 {times} 10{sup {minus}4}{mi… more
Date: December 31, 1992
Creator: Park, J. Y.; Shack, W. J. & Diercks, D. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fracture toughness measurements with subsize disk compact specimens

Description: Special fixtures and test methods have been developed for testing small disk compact specimens (1.25 mm diam by 4.6 mm thick). Specimens of European type 316L austenitic stainless steel were irradiated to damage levels of about 3 dpa at nominal irradiation temperatures of either 90 or 250 C and tested over a temperature range from 20 to 250 C. Results show that irradiation to this dose level at these temperatures reduces the fracture toughness but the toughness remains quite high. The toughness… more
Date: December 31, 1994
Creator: Alexander, D.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fabrication and closure development of nuclear waste disposal containers for the Yucca Mountain Project: Status report

Description: In GFY 89, a project was underway to determine and demonstrate a suitable method for fabricating thin-walled monolithic waste containers for service within the potential repository at Yucca Mountain. A concurrent project was underway to determine and demonstrate a suitable closure process for these containers after they have been filled with high-level nuclear waste. Phase 1 for both the fabrication and closure projects was a screening phase in which candidate processes were selected for furthe… more
Date: September 1, 1991
Creator: Domian, H. A.; Robitz, E. S.; Conrardy, C. C.; LaCount, D. F.; McAninch, M. D.; Fish, R. L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Robotic weld overlay coatings for erosion control. Quarterly technical progress report, April 1993--June 1993

Description: Twelve weld overlay hardfacing alloys have been selected for preliminary erosion testing based upon a literature review. Four of the selected coatings were deposited on a 1018 steel substrate using plasma arc welding process. During the past quarter, the remaining eight coatings were deposited in the same manner. Ten samples from each coatings were prepared for erosion testing. Microstructural characterization of each coating is in progress. This progress report describes coating deposition and… more
Date: July 20, 1993
Creator: Levin, B. F.; Dupont, J. N. & Marder, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thick-section weldments in 21-6-9 and 316LN stainless steel for fusion energy applications

Description: The Burning Plasma Experiment (BPX), formerly known as the Compact Ignition Tokomak, will be a major advance in the design of a fusion reactor. The successful construction of fusion reactors will require extensive welding of thick-section stainless steel plates. Severe service conditions will be experienced by the structure. Operating temperatures will range from room temperature (300 K) to liquid nitrogen temperature (77 K), and perhaps even lower. The structure will be highly stressed, and su… more
Date: January 1, 1991
Creator: Alexander, D. J. & Goodwin, G. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Triple ion-beam studies of radiation damage effects in a 316LN austenitic alloy for a high power spallation neutron source

Description: Austenitic 316LN alloy was ion-irradiated using the unique Triple Ion Beam Facility (TIF) at ORNL to investigate radiation damage effects relevant to spallation neutron sources. The TIF was used to simulate significant features of GeV proton irradiation effects in spallation neutron source target materials by producing displacement damage while simultaneously injecting helium and hydrogen at appropriately high gas/dpa ratios. Irradiations were carried out at 80, 200, and 350 C using 3.5 MeV Fe{… more
Date: September 1, 1997
Creator: Lee, E. H.; Rao, G. R.; Hunn, J. D.; Rice, P. M.; Lewis, M. B.; Cook, S. W. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Hydrogen retention in ion irradiated steels

Description: In the future 1--5 MW Spallation Neutron Source, target radiation damage will be accompanied by high levels of hydrogen and helium transmutation products. The authors have recently carried out investigations using simultaneous Fe/He,H multiple-ion implantations into 316 LN stainless steel between 50 and 350 C to simulate the type of radiation damage expected in spallation neutron sources. Hydrogen and helium were injected at appropriate energy and rate, while displacement damage was introduced … more
Date: November 1, 1998
Creator: Hunn, John D.; Lewis, M. B. & Lee, E. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion Experiments on Stainless Steels Used in Dry Storage Canisters of Spent Nuclear Fuel

Description: Nonradioactive (cold) experiments have been set up in the Idaho Chemical Processing Plant (ICPP)-1634, and radioactive (hot) experiments have been set up in the Irradiated Fuel Storage Facility (IFSF) at ICPP. The objective of these experiments is to provide information on the interactions (corrosion) between the spent nuclear fuel currently stored at the ICPP and the dry storage canisters and containment materials in which this spent fuel will be stored for the next several decades. This infor… more
Date: September 1, 1996
Creator: Ryskamp, J. M.; Adams, J. P.; Faw, E. M. & Anderson, P. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Robotic weld overlay coatings for erosion control. Quarterly technical progress report, October 1994--December 1994

Description: Research is presently being conducted to develop a criteria for selecting weld overlay coatings for erosion mitigation in Circulated Fluidized Beds. Initially, eleven weld overlay alloys were selected for erosion testing based upon a literature review. All eleven coatings were deposited on 1018 steel substrates using the plasma arc welding process. Ten samples from each coating were prepared for erosion testing. The coating deposition and sample preparation procedures were described in the seco… more
Date: January 25, 1995
Creator: Levin, B. F.; Dupont, J. N. & Marder, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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