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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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Characterization of two WESF (Waste Encapsulation and Storage Facility) capsules after five years of service

Description: Two Waste Encapsulation and Storage Facility (WESF) /sup 137/Cs capsules have been analyzed destructively after five years of service in the Sandia Irradiator for Dried Sewage Solids (SIDSS). The program concentrated on studies of the inner capsule, inner capsule weld areas, and analysis of the CsCl salt. No measurable corrosion was observed on the capsule wall or welds after the five years in the SIDSS Facility. The operating temperatures of the inner capsule wall were calculated to be between… more
Date: April 1, 1988
Creator: Sasmor, D. J.; Pierce, J. D.; Tingey, G. L.; Kjarmo, H. E.; Tills, J. & McKeon, D. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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WESF cesium capsule behavior at high temperature or during thermal cycling

Description: Double-walled stainless steel (SS) capsules prepared for storage of radioactive /sup 137/Cs from defense waste are now being considered for use as sources for commercial irradiation. Cesium was recovered at B-plant from the high-level radioactive waste generated during processing of defense nuclear fuel. It was then purified, converted to the chloride form, and encapsulated at the Hanford Waste Encapsulation and Storage Facility (WESF). The molten cesium chloride salt was encapsulated by pourin… more
Date: June 1, 1985
Creator: Tingey, G. L.; Gray, W. J.; Shippell, R. J. & Katayama, Y. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Creep of 304 LN and 316 L stainless steels at cryogenic temperatures

Description: Creep behavior of Type 304 LN plate and 316 L shielded-metal-arc (SMA)-deposited stainless weld metal was investigated at 4/sup 0/K. Testing was performed at constant load in a creep machine with a cryostat designed for long-term stability. Both transient and steady-state creep were observed during tests lasting over 2000 hours. Steady-state creep rates were much greater than expected from extrapolations of 300-K creep data. Creep rates on the order of 10/sup -10/ s/sup -1/ were observed at str… more
Date: August 7, 1985
Creator: Roth, L. D.; Manhardt, A. E.; Dalder, E. N. C. & Kershaw, R. P., Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Rapid heating tensile tests of high-energy-rate-forged 316L stainless steel charged with hydrogen and tritium

Description: Rapid heating tensile tests of uncharged, hydrogen-charged, and tritium-charged-and-aged stainless steels are being used to determine effects of internal hydrogen and helium on fracture modes and mechanical properties at elevated temperatures. Testing of high-energy-rate-forged (HERF) 316L stainless steel at temperatures up to near 1200{degree}C revealed that internal hydrogen has only slight effects on mechanical properties whereas internal helium from radioactive decay of tritium causes sever… more
Date: January 1, 1989
Creator: Mosley, W C
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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Welding stainless steels for structures operating at liquid helium temperature

Description: Superconducting magnets for fusion energy reactors require massive monolithic stainless steel weldments which must operate at extremely low temperatures under stresses approaching 100 ksi (700 MPa). A three-year study was conducted to determine the feasibility of producing heavy-section welds having usable levels of strength and toughness at 4.2/sup 0/K for fabrication of these structures in Type 304LN plate. Seven welding processes were evaluated. Test weldments in full-thickness plate were ma… more
Date: April 18, 1980
Creator: Witherell, C.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Strength and ductility of austenitic stainless steels irradiated in various fast reactor spectra

Description: Radiation damage cross sections derived from mechanical property changes in stainless steels 304, 316, and 308L decrease as the fast reactor spectrum softens from a mean neutron energy of 0.75 MeV to 0.2 MeV. Spectral sensitivity of 304 is greater than that of 316 and 308L weld deposits. Damage cross sections are generally consistent with existing empirical or theoretical damage models but do not verify the applicability of any one particular theoretical model. (FS)
Date: January 1, 1979
Creator: Blackburn, L. D.; Ward, A. L.; Simons, R. L. & Lippincott, E. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterization of an aged WESF capsule

Description: A joint effort by SNLA and ORNL was initiated for a detailed characterization of an 18-year-old WESF /sup 137/Cs source which has been used in the Sandia Irradiator for Dried Sewage Solids. The study included evaluation of the inner and outer stainless steel capsules by optical metallography, electron microprobe, and physical testing. Analysis of the residual atmospheres within the two containers was also done. The CsCl was analyzed for isotopic content and impurities. No potential problem area… more
Date: July 1, 1983
Creator: Kenna, B.T. & Schultz, F.J.
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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Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Description: Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of high-level radioactive-waste disposal containers. The waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The copper-based alloy materials are CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). The austenit… more
Date: August 1, 1988
Creator: Bullen, D. B. & Gdowski, G. E. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Description: Six alloys are being considered as possible materials for the fabrication of containers for the disposal of high-level radioactive waste. Three of these candidate materials are copper-based alloys: CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). The other three are iron- to nickel-based austenitic materials: Types 304L and 316L stainless steels and Alloy 825. Radioactive waste will include spent-fuel assemblies from reactors as well as waste in borosilicate glass and will… more
Date: August 1, 1988
Creator: Gdowski, G. E. & Bullen, D. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers

Description: Three iron- to nickel-based austenitic alloys (Types 304L and 316L stainless steels and Alloy 825) are being considered as candidate materials for the fabrication of high-level radioactive-waste containers. Waste will include fuel assemblies from reactors as well as high-level waste in borosilicate glass forms, and will be sent to the prospective repository at Yucca Mountain, Nevada. The decay of radionuclides in the repository will result in the generation of substantial heat and in fluences o… more
Date: April 1, 1988
Creator: Farmer, J. C.; Van Konynenburg, R. A.; McCright, R. D. & Bullen, D. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of irradiation and thermal aging upon fatigue-crack growth behavior of reactor pressure boundary materials. [Neutrons]

Description: Two processes that have the potential to produce degradation in the properties of pressure boundary materials are neutron irradiation and long-time thermal aging. This paper uses linear-elastic fracture mechanics techniques to assess the effect of these two processes upon the fatigue-crack growth behavior of a number of alloys commonly employed in reactor pressure boundaries. The materials evaluated include ferritic steels, austenitic stainless steels, and nickel-base alloys typical of those em… more
Date: October 1, 1978
Creator: James, L. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Cesium Chloride Compatibility Testing Program. Annual Report, Fiscal Year 1982

Description: A program was started in FY 1982 to evaluate the compatibility of WESF-produced CsCl with 316 L stainless steel under the thermal conditions that would be encountered in a geologic repository. The program is funded through the Long-Term High-Level Defense Waste Program of the Department of Energy. The major part of the program involves compatibility testing of six standard WESF CsCl capsules at a maximum CsCl/metal interface temperature of 450/sup 0/C. The capsules are allowed to self-heat to t… more
Date: December 1, 1982
Creator: Fullam, H. T.
Item Type: Refine your search to only Report
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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