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Criteria for Preparing and Packaging Plutonium Metals and Oxides for Long-Term Storage

Description: This Standard provides criteria for packaging of plutonium metals and stabilized oxides for storage periods of at least 50 years. To meet the criteria, plutonium-bearing materials must be in stable forms and be packaged in containers designed to maintain their integrity both under normal storage conditions and during anticipated handling accidents.
Date: December 1, 1994
Partner: UNT Libraries Government Documents Department

RECOVERY OF Np$sup 237$ AND Pu$sup 238$ FROM IRRADIATED NEPTUNIUM OXIDE

Description: An ion exchange process was demonstrated for the recovery of Pu/sup 238/ from irradiated neptunium oxide. Three cycles of anion exchange proved adequate for the removal of fission products and for the separation of the neptunium and plutonium from each other. (auth)
Date: November 1, 1959
Creator: Burney, G.A. & Prohaska, C.A.
Partner: UNT Libraries Government Documents Department

CHEMICAL PROCESSING OF Pu$sup 23$$sup 8$

Description: Plutonium (principally Pu/sup 238/) was separated from neptunium, and both the plutonium and neptunium were purified from fission products and cations by a three-cycle anion exchange process. (auth)
Date: October 1, 1962
Creator: Tetzlaff, R.N.
Partner: UNT Libraries Government Documents Department

Monthly Progress Report Heat Source Technology Programs September 1996

Description: This monthly report describes activities performed in support of Cassini fueled-clad production and studies related to the use of 238Pu02 in radioisotope power systems carried out for the Office of Special Applications of the U.S. Department of Energy (DOE) by Los Alamos National Laboratory (LANL). Most of the activities described are ongoing; the results and conclusions described may change as the work progresses.
Date: December 1, 1998
Creator: George, T. G.
Partner: UNT Libraries Government Documents Department

Monthly Progress Report Heat Source Technology Programs October through December 1996

Description: This quarterly report describes activities performed in support of Cassini fueled-clad production and studies related to the use of 238Pu02 in radioisotope power systems carried out for the Office of Special Applications of the U.S. Department of Energy (DOE) by Los Alamos National Laboratory (LANL). Most of the activities described are ongoing; the results and conclusions described may change as the work progresses.
Date: December 1, 1998
Creator: George, T. G.
Partner: UNT Libraries Government Documents Department

Radionuclide Concentration in Soils and Vegetation at Low-Level Radioactive Waste Disposal Area G during 2005

Description: Soil samples were collected at 15 locations and unwashed overstory and understory vegetation samples were collected from up to nine locations within and around the perimeter of Area G, the primary disposal facility for low-level radioactive solid waste at Los Alamos National Laboratory (LANL). Soil and plant samples were also collected from the proposed expansion area west of Area G for the purpose of gaining preoperational baseline data. Soil and plant samples were analyzed for radionuclides that have shown a history of detection in past years; these included {sup 3}H, {sup 238}Pu, {sup 239,240}Pu, {sup 241}Am, {sup 234}U, {sup 235}U, and {sup 238}U for soils and {sup 3}H, {sup 238}Pu, and {sup 239,240}Pu for plants. As in previous years, the highest levels of {sup 3}H in soils and vegetation were detected at the south portion of Area G near the {sup 3}H shafts; whereas, the highest concentrations of the Pu isotopes were detected in the northern and northeastern portions near the pads for transuranic waste. All concentrations of radionuclides in soils and vegetation, however, were still very low (pCi range) and far below LANL screening levels and regulatory standards.
Date: October 1, 2005
Creator: Fresquez, P.R.; McNaughton, M.W. & Winch, M.J.
Partner: UNT Libraries Government Documents Department

Mound Laboratory plutonium study: Presentation to the scientific review panel

Description: This paper describes the Mound plutonium study. The objectives of the project were to evaluate the inventory of plutonium 238 in the environment at Mound, determine the source, and alleviate potential health hazards. Analysis of soils, water, vegetation, fishes, and runoff were performed.
Date: February 19, 1975
Creator: Rogers, D. R.; Westendorf, W. H. & McClain, J. R.
Partner: UNT Libraries Government Documents Department

Human radiation studies: Remembering the early years. Oral history of Health physicist William J. Bair, Ph.D., October 14, 1994

Description: This report is a transcript of an interview of William J. Blair by representatives of the US DOE Office of Human Radiation Experiments. Dr. Blair was selected for this interview because of of his participation in the University of Rochester Atomic Energy Project and for his radiological inhalation research at Hanford Site. After a brief biographical sketch Dr. Blair discusses his remembrances on a wide rage of topics. Discussions include his graduate studies at Rochester University, use of human subjects at Rochester, his inhalation studies, his limited involvement with human studies, differing biological effects of plutonium 238 and 239, emissions from proposed nuclear-propelled aircraft, cancer research, cleanup at Nevada Test Site and Marshall Islands, impact of Langham studies to understand Plutonium exposure, and AEC controversies and colleagues.
Date: June 1, 1995
Creator: Harrell, D. & Shindledecker, C.
Partner: UNT Libraries Government Documents Department

Radionuclide analysis using solid phase extraction disks

Description: The use of solid phase extraction disks was studied for the quantification of selected radionuclides in aqueous solutions. The extraction of four radionuclides using six types (two commercial, four test materials) of 3M Empore{trademark} RAD disks was studied. The radionuclides studied were: technetium-99 (two types of disks), cesium-137 (two types), strontium-90 (one type), plutonium-238 (one type). Extractions were tested from DI water, river water and seawater. Extraction efficiency, kinetics (flow rate past the disk), capacity, and potential interferences were studied as well as quantification methods.
Date: December 1996
Creator: Beals, D. M; Britt, W. G.; Bibler, J. P. & Brooks, D. A.
Partner: UNT Libraries Government Documents Department

Overview of advanced technologies for stabilization of {sup 238}Pu-contaminated waste

Description: This paper presents an overview of potential technologies for stabilization of {sup 238}Pu-contaminated waste. Los Alamos National Laboratory (LANL) has processed {sup 238}PuO{sub 2} fuel into heat sources for space and terrestrial uses for the past several decades. The 88-year half-life of {sup 238}Pu and thermal power of approximately 0.6 watts/gram make this isotope ideal for missions requiring many years of dependable service in inaccessible locations. However, the same characteristic which makes {sup 238}Pu attractive for heat source applications, the high Curie content (17 Ci/gram versus 0.06 Ci/gram for 239{sup Pu}), makes disposal of {sup 238}Pu-contaminated waste difficult. Specifically, the thermal load limit on drums destined for transport to the Waste Isolation Pilot Plant (WIPP), 0.23 gram per drum for combustible waste, is impossible to meet for nearly all {sup 238}Pu-contaminated glovebox waste. Use of advanced waste treatment technologies including Molten Salt Oxidation (MSO) and aqueous chemical separation will eliminate the combustible matrix from {sup 238}Pu-contaminated waste and recover kilogram quantities of {sup 238}PuO{sub 2} from the waste stream. A conceptual design of these advanced waste treatment technologies will be presented.
Date: February 1, 1998
Creator: Ramsey, K.B.; Foltyn, E.M. & Heslop, J.M.
Partner: UNT Libraries Government Documents Department

Area G Perimeter Surface-Soil Sampling Environmental Surveillance for Fiscal Year 1998 Hazardous and Solid Waste Group (ESH-19)

Description: Material Disposal Area G (Area G) is at Technical Area 54 at Los Alamos National Laboratory (LANL). Area G has been the principal facility for the disposal of low-level, solid-mixed, and transuranic waste since 1957. It is currently LANL's primary facility for radioactive solid waste burial and storage. As part of the annual environmental surveillance effort at Area G, surface soil samples are collected around the facility's perimeter to characterize possible radionuclide movement off the site through surface water runoff During 1998, 39 soil samples were collected and analyzed for percent moisture, tritium, plutonium-238 and 239, cesium-137 and americium-241. To assess radionuclide concentrations, the results from these samples are compared with baseline or background soil samples collected in an undisturbed area west of the active portion Area G. The 1998 results are also compared to the results from analogous samples collected during 1996 and 1997 to assess changes over this time in radionuclide activity concentrations in surface soils around the perimeter of Area G. The results indicate elevated levels of all the radionuclides assessed (except cesium-137) exist in Area G perimeter surface soils vs the baseline soils. The comparison of 1998 soil data to previous years (1996 and 1997) indicates no significant increase or decrease in radionuclide concentrations; an upward or downward trend in concentrations is not detectable at this time. These results are consistent with data comparisons done in previous years. Continued annual soil sampling will be necessary to realize a trend if one exists. The radionuclide levels found in the perimeter surface soils are above background but still considered relatively low. This perimeter surface soil data will be used for planning purposes at Area G, techniques to prevent sediment tm.nsport off-site are implemented in the areas where the highest radionuclide concentrations are indicated.
Date: September 1, 1999
Creator: Childs, Marquis
Partner: UNT Libraries Government Documents Department

Low energy gamma-transitions in Pu{sup 238} and Pu{sup 240}

Description: We investigated electron and gamma spectra of mixtures of isotopes of curium. This was done on a beta spectrometer with double focusing at an angle of {pi}{radical}2 and on a scintillation gamma spectrometer with a 40 {times} 40 mm NAI(Tl) single crystal detector. The observed electron spectrum are interpolated and presented. Also, experimental results of the ratio of conversion at L and M subshells are presented and compared to theoretical values.
Date: March 27, 1967
Creator: Akalaev, G. G.; Vartanov, N. A. & Samoilov, P. S.
Partner: UNT Libraries Government Documents Department