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Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: April--June 1977

Description: Ultrafication (UF) membranes have demonstrated 90 to 98% rejection of gross alpha in laboratory tests. In the treatment of laundry wastes, rejection of activity ranged from 98 to 99.9% gross alpha. The pilot UF system was installed and started up. Flux decline curves and volume reduction performance were determined. Volume reductions of 210 : 1 were achieved at flux rates of 1.1 gal/min (system is rated at 2 to 3 gal/min, 90% recovery) at activity rejection of 99.94% gross alpha. Adsorbent stud… more
Date: November 14, 1977
Creator: Koenst, J. W.; Herald, W. R. & Roberts, R. C.
Partner: UNT Libraries Government Documents Department
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Environmental and radiological safety studies. Interaction of /sup 238/PuO/sub 2/ heat sources with terrestrial and aquatic environments. Progress report, July 1--September 30, 1977

Description: The containers for /sup 238/PuO/sub 2/ heat sources in radioisotope thermoelectric generators are designed with large safety factors to ensure that they will withstand reentry from orbit and impact with the earth and safely contain the nuclear fuel until it is recovered. Existing designs have proved more than adequately safe, but the Office of the Assistant Director for Space Application of the ERDA Division of Nuclear Research and Application continually seeks more information about the heat s… more
Date: November 1, 1977
Creator: Waterbury, G.R. (comp.)
Partner: UNT Libraries Government Documents Department
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Pu-238 production at the Savannah River Plant

Description: Pu-238 production capability at SRP is dependent on the availability of Np-237 feed material. With continuing operation of three production reactors at SRP, production of 46 kg Pu-238 per year can be sustained. Capacity of auxiliary facilities is adequate to support the production rates.
Date: November 1, 1987
Creator: Roggenkamp, P.L.
Partner: UNT Libraries Government Documents Department
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Double beta decay of U-238

Description: During the last period, two samples of 33 yr old uranyl nitrate have been examined for the accumulation of Pu-238 formed as a result of double beta decay. The 2.5 kg sample has led only to an upper limit of 6 {times} 10{sup 20} yr. The 8.5 kg sample has produced positive results corresponding to a half-life of 2 {times} 10{sup 21 } yr. The possibility of contaminating nuclear reactions has been carefully examined and eliminated. The possibility that contamination may have been introduced by the… more
Date: November 1, 1990
Creator: Turkevich, A. & Economou, T.
Partner: UNT Libraries Government Documents Department
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Long-term exposure of pressed plutonium oxide heat sources to aquatic environments

Description: Plutonium-238 oxide fuel pellets were exposed to water for 2.5 to 6.4 yr, and the concentration of plutonium in the water was monitored. Water composition and temperature were found to be important factors in determining the rate of plutonium release into the water. Typical release rates ranged from 10 to 40 ng/m/sup 2//s in cold fresh water and from 0.3 to 11 ng/m/sup 2//s in cold sea water. Release rates in sea water varied over time and sometimes were erratic. The plutonium release per unit … more
Date: November 1, 1984
Creator: Heaton, R. C.; Patterson, J. H.; Kosiewicz, S. T.; Matlack, G. M.; Steinkruger, F. J.; Nelson, G. B. et al.
Partner: UNT Libraries Government Documents Department
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Industrial safety and applied health physics. Annual report for 1980

Description: Information is reported in sections entitled: radiation monitoring; Environmental Management Program; radiation and safety surveys; industrial safety and special projects; Office of Operational Safety; and training, lectures, publications, and professional activities. There were no external or internal exposures to personnel which exceeded the standards for radiation protection as defined in DOE Manual Chapter 0524. Only 35 employees received whole body dose equivalents of 10 mSv (1 rem) or gre… more
Date: November 1, 1981
Partner: UNT Libraries Government Documents Department
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Potential Health Risks From Postulated Accidents Involving the Pu-238 RTG (Radioisotope Thermoelectric Generator) on the Ulysses Solar Exploration Mission

Description: Potential radiation impacts from launch of the Ulysses solar exploration experiment were evaluated using eight postulated accident scenarios. Lifetime individual dose estimates rarely exceeded 1 mrem. Most of the potential health effects would come from inhalation exposures immediately after an accident, rather than from ingestion of contaminated food or water, or from inhalation of resuspended plutonium from contaminated ground. For local Florida accidents (that is, during the first minute aft… more
Date: November 2, 1990
Creator: Goldman, M. (California Univ., Davis, CA (USA)); Nelson, R.C. (EG and G Idaho, Inc., Idaho Falls, ID (USA)); Bollinger, L. (Air Force Inspection and Safety Center, Kirtland AFB, NM (USA)); Hoover, M.D. (Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (USA). Inhalation Toxicology Research Inst.); Templeton, W. (Pacific Northwest Lab., Richland, WA (USA)) & Anspaugh, L. (Lawren
Partner: UNT Libraries Government Documents Department
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Request for One-Time Shipment of 32 Watt PU-328 Source in 9968 Packaging

Description: The 9968 package is designed for surface shipment of fissile and other radioactive materials where a high degree of double containment is required. The use of the 9968 radioactive material package for a one time shipment of a 32 watt heat source versus the SARP approved maximum 30 watt heat source is addressed in this report. The analyses show that the small increase in heat load from 30 watts to 32 watts does not substantially increase internal temperatures or pressures that would approach lim… more
Date: November 25, 1998
Creator: Massey, W.M.
Partner: UNT Libraries Government Documents Department
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In Vivo Measurement of Actinides in the Human Lung. [Calibration and Comparison of Phoswich, Large-Area Proportional Counter, and Intrinsic Germanium Planar Array Detector Systems]

Description: The problems associated with the in vivo detection and measurement of actinides in the human lung are discussed together with various measurement systems currently in use. In particular, the methods and calibration procedures employed at the Lawrence Livermore Laboratory, namely, the use of twin Phoswich detectors and a new, more realistic, tissue-equivalent phantom, are described. Methods for the measurement of chest-wall thickness, fat content, and normal human background counts are also disc… more
Date: November 6, 1979
Creator: Anderson, A. L.; Campbell, G. W. & Griffith, R. V.
Partner: UNT Libraries Government Documents Department
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Environmental and radiological safety studies. Interaction of /sup 238/PuO/sub 2/ heat sources with terrestrial and aquatic environments. Progress report, July 1-September 25, 1981

Description: Although existing radioisotope thermoelectric generator designs have proved more than adequately safe, more information is continually sought about the heat sources to improve their safety. The work here includes studies of the effects on the heat sources of terrestrial and aquatic environments and also of the effects of the heat sources on various simulated environments. This progress report presents recent data from environmental chamber and aquatic experiments and gives the present status of… more
Date: November 1, 1981
Creator: Matlack, G. M. & Patterson, J. H.
Partner: UNT Libraries Government Documents Department
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Technical background information for the environmental and safety report, Volume 5: the 1977 Clinch River sediment survey - data presentation

Description: This study determined the fate and distribution of nuclides in the Clinch River by analyzing selected cores for transuranic radionuclide activity and examined the effect of the altered flow regime in the Clinch River on the distribution of the fission product activity. Cores were collected along the full length of the Clinch River from the WOC outfall (CRM 20.8) to locations in the Tennessee River on either side of the junction of the two rivers. The sampling was concentrated around CRM 20.8 an… more
Date: November 1, 1982
Creator: Oakes, T. W.; Ohnesorge, W. F.; Eldridge, J. S.; Scott, T. G.; Parsons, D. W.; Hubbard, H. M. et al.
Partner: UNT Libraries Government Documents Department
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/sup 238/Pu fuel form processes. Bimonthly report, November-December 1979

Description: Progress in the Savannah River Laboratory's /sup 238/Pu Fuel Form Program is summarized. Full-scale fabrication tests continued in the Plutonium Experimental Facility (PEF) with the successful fabrication of seven additional GPHS pellets. Three pellets (GPHS Pellets 14, 15, and 16) were fabricated at off-centerline conditions to help define process limits for production of GPHS fuel pellets in the Plutonium Fuel Fabrication (PuFF) Facility. Two additional limit-test pellets (GPHS Pellets 12 and… more
Date: November 1, 1980
Partner: UNT Libraries Government Documents Department
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Review of measurement techniques for stack monitoring of long-lived alpha emitters

Description: As a result of the promulgation of new guidelines by the Environmental Protection Agency (40 CFR 190) for releases of long-lived, alpha-emitting substances, the stack-monitoring requirements for measuring long-lived alpha particles may change in terms of both monitored isotopes and the detection levels. This paper briefly reviews stack-monitoring requirements for long-lived alpha-emitting particles. It also examines the currently deployed alpha-particulate, stack-monitoring systems and discusse… more
Date: November 1, 1978
Creator: Kordas, J. F. & Phelps, P. L.
Partner: UNT Libraries Government Documents Department
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Research and development allocations and plant assistance support, FY-1966

Description: This report discusses an allocation of $1,320,000 of 02 Reactor and Metallurgy funds which was previously made to the Pacific Northwest Laboratories. The Process Technology work order support which N-Reactor Department expected to provide during FY 1966 was estimated. The R&D allocation was based on the 189 budget proposals which were prepared early in 1965 and program identifications were provided. The integrated five year research and development program was subsequently formulated with the a… more
Date: November 22, 1965
Creator: Leverett, M. C.
Partner: UNT Libraries Government Documents Department
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17-keV x-ray output of plutonium

Description: In the production of plutonium in a reactor, plutonium-238, 240, and 241 are formed as well as Pu{sup 239}. It is well known that the specific alpha activity of the plutonium varies as the percentages of these isotopes are changed. Kinderman, et al have worked out the relationship between isotopic content and MWD/ton exposure. Their findings are reported in this document.
Date: November 5, 1958
Creator: McCall, R. C. & Bernard, R. M.
Partner: UNT Libraries Government Documents Department
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Uranium daughter growth must not be neglected when adjusting plutonium materials for assay and isotopic contents

Description: Relationships are provided to compute the decreasing plutonium content and changing isotopic distribution of plutonium materials for the radioactive decay of /sup 238/Pu, /sup 239/Pu, /sup 240/Pu and /sup 242/Pu to long-lived uranium daughters and of /sup 241/Pu to /sup 241/Am. This computation is important to the use of plutonium reference materials to calibrate destructive and nondestructive methods for assay and isotopic measurements, as well as to accountability inventory calculations.
Date: November 1, 1976
Creator: Marsh, S. F.; Spall, W. D.; Abernathey, R. M. & Rein, J. E.
Partner: UNT Libraries Government Documents Department
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Performance of multiple HEPA filters against plutonium aerosols

Description: Performance of multiple stages of high-efficiency particulate air (HEPA) filters has been verified against plutonium aerosols similar in size characteristics to those challenging the air-cleaning systems of plutonium-processing facilities. An experimental program was conducted to test each filter in systems of three HEPA filters operated in series against /sup 238/PuO/sub 2/ aerosols as high as 3.3 x 10/sup 10/ dis/s . m/sup 3/ in activity concentration and ranging from 0.22 ..mu..m to 1.6 ..mu… more
Date: November 1, 1976
Creator: Gonzales, M.; Elder, J. C.; Tillery, M. I. & Ettinger, H. J.
Partner: UNT Libraries Government Documents Department
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/sup 238/Pu surface contamination of MHW impact shell assembly

Description: /sup 238/PuO/sub 2/ contamination of the grit blasted surface of the primary impact shell assembly (PISA) of the multi-hundred watt isotopic heat source was measured. The study determined the amount and distribution of the /sup 238/PuO/sub 2/ and characterization of its behavior during aging at 1350/sup 0/C. The results concluded that normal decontamination effectively removes the superficial /sup 238/PuO/sub 2/ but does not extract the /sup 238/PuO/sub 2/ which is deep within the grit blasted … more
Date: November 22, 1976
Creator: Schaeffer, D. R.; Johnson, E. W.; Sheehan, W. E.; Fleming, D. L. & Egleston, E. E.
Partner: UNT Libraries Government Documents Department
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Fabrication of a 238Pu target

Description: Precision neutron-induced reaction data are important for modeling the network of isotope production and destruction within a given diagnostic chain. This network modeling has many applications such as the design of advanced fuel cycle for reactors and the interpretation of radiochemical data related to the stockpile stewardship and nuclear forensics projects. Our current funded effort is to improve the neutron-induced reaction data on the short-lived actinides and the specific goal is to impro… more
Date: November 16, 2010
Creator: Wu, C Y; Chyzh, A; Kwan, E; Henderson, R; Gostic, J & Carter, D
Partner: UNT Libraries Government Documents Department
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Probabilistic performance-assessment modeling of the mixed waste landfill at Sandia National Laboratories.

Description: A probabilistic performance assessment has been conducted to evaluate the fate and transport of radionuclides (americium-241, cesium-137, cobalt-60, plutonium-238, plutonium-239, radium-226, radon-222, strontium-90, thorium-232, tritium, uranium-238), heavy metals (lead and cadmium), and volatile organic compounds (VOCs) at the Mixed Waste Landfill (MWL). Probabilistic analyses were performed to quantify uncertainties inherent in the system and models for a 1,000-year period, and sensitivity an… more
Date: November 1, 2005
Creator: Peace, Gerald L.; Goering, Timothy James (GRAM, Inc.); Miller, Mark Laverne & Ho, Clifford Kuofei
Partner: UNT Libraries Government Documents Department
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