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Radionuclides in plankton from the South Pacific Basin

Description: We have initiated an investigation of the utility of marine plankton as bioconcentrating samplers of low-level marine radioactivity in the southern hemisphere. A literature review has shown that both freshwater and marine plankton have trace element and radionuclide concentration factors (relative to water) of up to 10/sup 4/. We participated in Operations Deepfreeze 1981 and 1982, collecting a total of 48 plankton samples from the USCGC Glacier on its Antarctic cruises. Battelle Pacific Northw… more
Date: March 23, 1984
Creator: Marsh, K.V. & Buddemeier, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Source-jerk analysis using a semi-explicit inverse kinetic technique

Description: A method is proposed for measuring the effective reproduction factor, k, in subcritical systems. The method uses the transient response of a subcritical system to the sudden removal of an extraneous neutron source (i.e., a source jerk). The response is analyzed using an inverse kinetic technique that least-squares fits the exact analytical solution corresponding to a source-jerk transient as derived from the point-reactor model. It has been found that the technique can provide an accurate means… more
Date: January 1, 1985
Creator: Spriggs, G.D. & Pederson, R.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Management of radioactive waste gases from the nuclear fuel cycle. Volume I. Comparison of alternatives

Description: Alternatives were compared for collection and fixation of radioactive waste gases released during normal operation of the nuclear fuel cycle, and for transportation and storage/disposal of the resulting waste forms. The study used a numerical rating scheme to evaluate and compare the alternatives for krypton-85, iodine-129, and carbon-14; whereas a subjective evaluation, based on published reports and engineering judgement, was made for transportation and storage/disposal options. Based on thes… more
Date: December 1, 1980
Creator: Evans, A. G.; Prout, W. E.; Buckner, J. T. & Buckner, M. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Long-lived heavy mass elements half-lives (A > 125)

Description: Reported values of half-lives of intermediate mass and heavy elements are evaluated. The evaluation analysis estimates the systematic error the resulting standard deviation. Recommended values are then presented for /sup 128/Te, /sup 130/Te, /sup 129/I, /sup 138/La, /sup 144/Nd, /sup 145/Nd, /sup 146,147,148/Sm, /sup 152/Gd, /sup 154/Dy, /sup 176/Lu, /sup 174/Hf, /sup 180/Ta, /sup 187/Re, /sup 186/Os, /sup 190/Pt, /sup 204,205/Pb, and /sup 230,232/Th. 103 refs., 21 tabs. (WRF)
Date: January 1, 1985
Creator: Holden, Norman E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Leaching studies of low-level radioactive waste forms

Description: A research program has been under way at the Brookhaven National Laboratory to investigate the radionuclide release behavior of ion exchange bead resin waste solidified in Portland cement. An important aspect of this program is to develop and evaluate testing procedures and methodologies which enable the long-term performance evaluation of waste forms under simulated field conditions. Cesium and strontium release behavior using a range of testing procedures, including intermittent leachant flow… more
Date: January 1, 1985
Creator: Dayal, R.; Arora, H.; Clinton, J.C. & Milian, L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Input and decayed values of radioactive liquid wastes discharged to the ground in the 200 Areas through 1975

Description: Low and intermediate level liquid wastes from chemical separations processing of spent reactor fuel elements have been discharged to the ground in the 200-Areas since 1944. Large volumes of process cooling water, normally free of radioactive contaminants, are discharged to surface ditches or natural surface depressions (ponds). Lesser volumes of liquid waste such as steam condensates, process condensates, scavenged process waste supernatants, and plutonium processing wastes have been, or are be… more
Date: July 8, 1976
Creator: Anderson, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Soviet American Gallium Experiment (SAGE)

Description: A radiochemical experiment using the reaction v/sub e/ = /sup 71/Ga + e/sup e/ to determine the integral flux of low-energy neutrinos from the sun is currently under preparation at the Baksan Neutrino Observatory in the USSR. Measurements are scheduled to commence by late 1988 using /approximately/30 tonnes of metallic gallium. With this amount of gallium it should be possible to obtain a fractional statistical accuracy of 12 to 15% after one year (assuming the standard solar model neutrino flu… more
Date: January 1, 1988
Creator: Abazov, A. I.; Abdurashitov, D. N.; Anosov, O. P.; Avdeyev, A. V.; Belousko, Yu. I.; Bychuk, O. V. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Study of Isovector Resonances With Pion Charge Exchange

Description: Studies with the pion charge exchange reactions (..pi../sup +-/,..pi../sup 0/) at 164 MeV using the LAMPF ..pi../sup 0/ spectrometer are yielding new results on the existence and systematic features of isovector resonances in nuclei. These experiments possess an unusually high signal/background ratio for isovector resonances of low-multipolarity. Results obtained to date are: (1) observation and angular disribution measurement of the giant dipole resonance in nuclei /sup 12/C, /sup 40/Ca, /sup … more
Date: January 1, 1982
Creator: Baer, H.W.; Bolton, R. & Bowman, J.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Transport and deposition of activation products in a helium cooled fusion power plant

Description: The transport and deposition of neutron activation products in a helium cooled tokamak fusion power plant are investigated. Stainless steel is used as coolant channel material for a helium/steam system. The important gamma emitting nuclides /sup 56/Mn, /sup 54/Mn, /sup 57/Co, /sup 58/Co, /sup 60/Co, /sup 51/Cr, and /sup 99/Mo are considered. The dominant release mechanism identified is direct daughter recoil emission from (n,x) type reactions. Corrosion and evaporation are discussed. The radion… more
Date: September 1, 1980
Creator: Bickford, W.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of the radionuclide concentrations in soil and plants from the 1975 terrestrial survey of Bikini and Eneu Islands

Description: In June 1975 a radiological survey was conducted of the terrestrial environment of Bikini and Eneu islands (Bikini Atoll) to evaluate the potential radiation dose to the returning Bikini population. In this report, we present measurements of the radionuclide concentration in soil profiles and in dominant species of edible and nonedible, indicator plants. The use of these data to derive relationships to predict the plant uptake of radionuclides from soil is described. Approximately 620 soil and … more
Date: January 21, 1977
Creator: Colsher, C. S.; Robison, W. L. & Gudiksen, P. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of technetium uptake in vegetation in the vicinity of the Portsmouth Gaseous Diffusion Plant

Description: Technetium-99 was measured in vegetation and soil collected on and near the Portsmouth Gaseous Diffusion Plant to obtain an estimate of the soil-to-vegetation concentration factors. The concentration factors appear to be lognormally distributed with a geometric mean of 3.4 (Bq/kg dry wt. tissue per Bq/kg dry wt. soil) and a geometric standard deviation of 4.7. A dose commitment was calculated using a hypothetical 3.7 x 10/sup 10/ Bq Tc-99/year release and the actual CY-1981 concentration releas… more
Date: January 1, 1982
Creator: Acox, T.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of homogeneous U233 and U235 critical assemblies with ENDF/B-IV data (AWBA development program)

Description: Thirty-two U233 and U235 homogeneous aqueous critical experiments were analyzed with ENDF/B-IV data. Calculated eigenvalues for both fuel types increased by nearly 2 percent over the range of hydrogen/uranium atomic ratio covered (from 2106 to 27.1). This is attributed mostly to an underprediction of fast leakage, with some contribution from the fission and capture resonance integrals of ENDF/B-IV U235. Eigenvalue sensitivities to several nuclear data changes were examined. Values of the therma… more
Date: October 1977
Creator: Ullo, J.J. & Hardy, J. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Annual hydrologic data summary for the White Oak Creek Watershed: Water Year 1990 (October 1989--September 1990)

Description: This report summarizes, for the Water Year 1990 (October 1989-- September 1990), the dynamic hydrologic data collected on the Whiteoak Creek (WOC) Watershed's surface and subsurface flow systems. These systems affect the quality or quantity of surface water and groundwater. The collection of hydrologic data is one component of numerous, ongoing Oak Ridge National Laboratory (ORNL) environmental studies and monitoring programs and is intended to 1. characterize the quantity and quality of water … more
Date: September 1, 1991
Creator: Borders, D. M.; Gregory, S. M.; Clapp, R. B.; Frederick, B. J.; Moore, G. K.; Watts, J. A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prediction of the migration of several radionuclides in ocean sediment with the computer code IONMIG: a preliminary report

Description: A computer code, IONMIG, which is used to calculate the far-field transport of radionuclides through ocean sediment by diffusion and convection is described. The code uses a two-dimensional, axisymmetric, explicit finite difference formulation. Preliminary results for several species (Cs, Pu, I, Tc) are given.
Date: May 1, 1980
Creator: Russo, A.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutronics of a mixed-flow gas-core reactor

Description: The study was made to investigate the neutronic feasibility of a mixed-flow gas-core reactor. Three reactor concepts were studied: four- and seven-cell radial reactors and a seven-cell scallop reactor. The reactors were fueled with UF/sub 6/ (either U-233 or U-235) and various parameters were varied. A four-cell reactor is not practical nor is the U-235 fueled seven-cell radial reactor; however, the 7-cell U-233 radial and scallop reactors can satisfy all design criteria. The mixed flow gas cor… more
Date: November 1, 1977
Creator: Soran, P. D. & Hansen, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Isotopic distributions, element ratios, and element mass fractions from enrichment-meter-type gamma-ray measurements of MOX

Description: The gamma-ray spectra from infinitely'' thick mixed oxide samples have been measured. The plutonium isotopics, the U/Pu ratio, the high-Z mass fractions (assuming only plutonium, uranium, and americium), and the low-Z mass fraction (assuming the matrix is only oxygen) can be determined by carefully analyzing the data. The results agree well with the chemical determination of these parameters. 8 refs., 3 figs., 3 tabs.
Date: January 1, 1991
Creator: Close, D. A.; Parker, J. L.; Haycock, D. L. & Dragnev, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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End of life fission product distributions in F-1 experiment fuel rods

Description: Fission product migration and end-of-life distributions were examined in the F-1 (X094) series of sealed, mixed-oxide fuel rods irradiated in the fast flux of EBR-II. Cesium, rubidium, iodine, and strontium data obtained from axial gamma scanning, mass spectrometry, and radiochemical analyses are presented. The results show significant migration of cesium, probably as both a volatile species and as the noble gas precursor. Cesium metal species leaving the fuel region accumulate predominately at… more
Date: May 1, 1980
Creator: Goodin, D. T.; Langer, S. & Bell, W. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Po-210 as long-term integrating radon indicator in the indoor environment

Description: The general objective is to improve the knowledge about the transferring processes leading from airborne radon/radon daughters to embedded Po-210 in hard surfaces in the indoor environment. The specific goal of the research is to identify situations in which the surface activity of Po-210 can be used as a long-term indicator of lung cancer risk from past or future radon exposures.
Date: July 1, 1990
Creator: Samuelsson, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Post-remedial-action radiological survey of the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pennsylvania, October 1-8, 1981

Description: The post-remedial-action radiological assessment conducted by the ANL Radiological Survey Group in October 1981, following decommissioning and decontamination efforts by Westinghouse personnel, indicated that except for the Advanced Fuels Laboratory exhaust ductwork and north wall, the interior surfaces of the Plutonium Laboratory and associated areas within Building 7 and the Advanced Fuels Laboratory within Building 8 were below both the ANSI Draft Standard N13.12 and NRC Guideline criteria f… more
Date: January 1, 1984
Creator: Flynn, K. F.; Justus, A. L.; Sholeen, C. M.; Smith, W. H. & Wynveen, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A review of the Y-12 Plant discharge of enriched uranium to the sanitary sewer (DEUSS)

Description: The Oak Ridge Y-12 Plant is situated adjacent to the Oak Ridge city limits and is operated by the United States Department of Energy (DOE). The Y-12 Plant is located on 4,860 acres, which is collectively referred to as the Y-12 Plant site. Among the missions for which the facility is in existence are producing nuclear weapons components, supporting weapon design laboratories, and processing special nuclear materials (SNM). The Y-12 Plant is under the regulatory guidance of DOE Order 5400.5 and … more
Date: September 1, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cobalt-60 heat source demonstration program. Phase III. Fabrication. Final report

Description: Significant accomplishments completed during Phase III of the /sup 60/Co Heat Source Demonstration program include the following: encapsulation of 2 MCi of /sup 60/Co; fabrication of the heat source, including the ASME coded pressure vessel/core assembly, and biological shielding; endurance testing of a prototype heat pipe for a period of 28 months; fabrication and qualification of the heat pipe emergency cooling subsystem; issue of the safety evaluation report, reference 3, and the operations … more
Date: June 1, 1973
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Division quarterly progress report, October 1--December 31, 1977. [Fuel cycle research and development; special materials production]

Description: Results are presented on the fluidized-bed calcination of simulated radioactive waste from the reprocessing of spent commercial nuclear fuel and on the removal of actinide elements from the waste prior to calcination. Other programs include the development of storage technology for /sup 85/Kr waste; and the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel. The long-term management of defense waste from the ICPP covers post-calcination treatment of ICPP calcin… more
Date: February 1, 1978
Creator: Slansky, C.M. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sediment and radionuclide transport in rivers. Phase 3. Field sampling program for Cattaraugus and Buttermilk Creeks, New York

Description: A field sampling program was conducted on Cattaraugus and Buttermilk Creeks, New York during April 1979 to investigate the transport of radionuclides in surface waters as part of a continuing program to provide data for application and verification of Pacific Northwest Laboratory's (PNL) sediment and radionuclide transport model, SERATRA. Bed sediment, suspended sediment and water samples were collected during unsteady flow conditions over a 45 mile reach of stream channel. Radiological an… more
Date: August 1, 1982
Creator: Ecker, R. M.; Walters, W. H. & Onishi, Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Light water reactor fuel reprocessing: dissolution studies of voloxidized fuel

Description: Voloxidation is a proposed head-end process to remove tritium from irradiated LWR fuel by roasting the fuel in the presence of oxygen. The process oxidizes UO/sub 2/ to a fine U/sub 3/O/sub 8/ powder with high surface area for dissolution. Small-scale tests with irradiated Robinson, Oconee, and Saxton reactor fuels have been made to determine the dissolution behavior of both voloxidized and nonvoloxidized (UO/sub 2/) fuel. No significant technical problems were encountered in batch-dissolving o… more
Date: January 1, 1977
Creator: Johnson, D. R. & Stone, J. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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