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RADIATION EFFECTS ON EPOXY/CARBON FIBER COMPOSITE

Description: The Department of Energy Savannah River Site vitrifies nuclear waste incident to defense programs through its Defense Waste Processing Facility (DWPF). The piping in the DWPF seal pot jumper configuration must withstand the stresses during an unlikely but potential deflagration event, and maintain its safety function for a 20-year service life. Carbon fiber-reinforced epoxy composites (CFR) were proposed for protection and reinforcement of piping during such an event. The proposed CFR materials… more
Date: December 12, 2008
Creator: Hoffman, E & Eric Skidmore, E
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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DEMOLISHING A COLD WARE ERA FULE STORAGE BASIN SUPERSTRUCTURE LADEN WITH ASBESTOS

Description: The K East (KE) Basin facilities are located near the north end of the Hanford Site's 100 K area. The facilities were built in 1950 as part of the KE Reactor complex and constructed within 400 meters of the Columbia River, which is the largest river in the Pacific Northwest and by volume the fourth largest river in the United States. The basin, located adjacent to the reactor, was used for the underwater storage of irradiated nuclear fuel discharged from the reactor. The basin was covered by a … more
Date: January 12, 2009
Creator: ER, LLOYD; JM, STEVENS; EB, DAGAN; TK, ORGILL; MA, GREEN; CH, LARSON et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Small-Column Ion-Exchange Alternative to Remove 137Cs from Low-Curie Salt Waste: Summary of Phase 1

Description: A Small-Column Ion-Exchange (SCIX) system is being evaluated for removing cesium from the Type 2 and/or Type 3 dissolved saltcake wastes at the Savannah River Site (SRS) to ensure that the dissolved saltcake meets the waste acceptance criteria at the Saltstone Facility. Both crystalline silicotitanate (CST) and IONSIV{trademark} IE-96 zeolite were evaluated as the ion-exchange media. The accelerated alternative, using CST in the SCIX, could save as much as $3 billion in operating and storage co… more
Date: May 12, 2004
Creator: Walker, J. F. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Risk of Low Dose/Low Dose Rate Ionizing Radiation to Humans Symposium at the EMS 2009 Annual Meeting - September 2006

Description: The low dose symposium thoughtfully addressed controversy of risk from low dose radiation exposure, hormesis and radon therapy. The stem cell symposium cogently considered the role of DNA damage and repair in hematopoietic stem cells underlying aging and malignancy and provocatively presented evidence that stem cells may have distinct morphologies and replicative properties, as well as special roles in cancer initiation. In the epigenetics symposium, studies illustrated the long range interacti… more
Date: November 12, 2009
Creator: Morgan, William F.; von Borstel, Robert C.; Brenner, David; Redpath, J. Leslie; Erickson, Barbra E. & Brooks, Antone L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Benchmark Studies of Induced Radioactivity Produced in LHC Materials, Pt II Specific Activities

Description: A new method to estimate remanent dose rates, to be used with the Monte Carlo code FLUKA, was benchmarked against measurements from an experiment that was performed at the CERN-EU high-energy reference field facility. An extensive collection of samples of different materials were placed downstream of and laterally to a copper target, intercepting a positively charged mixed hadron beam with a momentum of 120 GeV/c. Emphasis was put on the reduction of uncertainties such as careful monitoring of … more
Date: April 12, 2006
Creator: Brugger, M.; Mayer, S.; Roesler, S.; Ulrici, L.; Khater, H.; Prinz, A. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Dose Rate Calucaltion for the DHL W/DOE SNF Codisposal Waste Package

Description: The purpose of this calculation is to determine the surface dose rates of the short codisposal waste package (WP) of defense high-level waste (DHLW) and TRIGA (Training, Research, Isotopes, General Atomics) spent nuclear fuel (SNF). The WP contains the TRIGA SNF, in a standardized 18-in. DOE (U.S. Department of Energy) SNF canister, and five 3-m-long Savannah River Site (SRS) DHLW pour glass canisters, which surround the DOE SNF canister.
Date: February 12, 2000
Creator: Radulescu, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Generalization of Spatial Channel Theory to Three-Dimensional x-y-z Transport Computations

Description: Spatial channel theory, initially introduced in 1977 by M. L. Williams and colleagues at ORNL, is a powerful tool for shield design optimization. It focuses on so called ''contributon'' flux and current of particles (a fraction of the total of neutrons, photons, etc.) which contribute directly or through their progeny to a pre-specified response, such as a detector reading, dose rate, reaction rate, etc., at certain locations of interest. Particles that do not contribute directly or indirectly … more
Date: March 12, 2002
Creator: Abu-Shumays, I. K.; Hunter, M. A.; Martz, R. L. & Risner, J. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Benchmark Studies of Induced Radioactivity Produced in LHC Materials, Pt I: Remanent Dose Rates

Description: Samples of materials which will be used in the LHC machine for shielding and construction components were irradiated in the stray radiation field of the CERN-EU high-energy reference field facility. After irradiation, the specific activities induced in the various samples were analyzed with a high-precision gamma spectrometer at various cooling times, allowing identification of isotopes with a wide range of half-lives. Furthermore, the irradiation experiment was simulated in detail with the FLU… more
Date: April 12, 2006
Creator: Brugger, M.; Mayer, S.; Roesler, S.; Ulrici, L.; Khater, H.; Prinz, A. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Source of process water scandium

Description: Rear face dose rates at the single pass reactors were found to have significantly increased between 1965 and 1967. It was suggested by Battelle-Northwest that an increase in scandium-46 activity may have been a possible cause of the increased dose rates. Battelle-Northwest records showed that considerably more {sup 46}Sc was present in the Columbia River at Richland starting in the summer of 1967 than had been found previously. The ratio of {sup 46}Sc to {sup 65}Zn activity, a correlation which… more
Date: June 12, 1970
Creator: Larrick, A. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of the Potential Impact of Gamma-Induced Radiolytic Gases on Loading of Cesium Onto Crystalline Silicotitanate Sorbent at ORNL's High Flux Isotope Reactor

Description: The use of an engineered form of crystalline silicotitanate as a potential sorbent for the removal and concentration of cesium from the high-level waste at the Savannah River Site was investigated. Results conclusively showed this sorbent to be unaffected by gamma-induced radiolytic gas formation during column loading. Closely controlled column-loading experiments were performed at the Oak Ridge National Laboratory's High Flux Isotope Reactor (HFIR) in a gamma field with a conservative dose rat… more
Date: February 12, 2001
Creator: Mattus, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Elemental analysis of as-built concrete and aluminum for the National Ignition Facility and their effect upon residual dose rates

Description: GDMS measurements provide final material compositions, which are compared to expected values. Finally, the calculations are repeated with the measured compositions and the residual dose rates are compared to the expected levels. 3-D neutronics calculations have been performed using the TART98 Monte Carlo transport code. Activation calculations have been completed with the ACAB activation code and the FENDL/A-2.0 activation cross section library. These codes have been benchmarked against experim… more
Date: August 12, 1999
Creator: Latkowski, J F & Sanz, J
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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