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Proposed plan for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

Description: The US Department of Energy (DOE) in compliance with Section 117(a) of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980, as amended by the Superfund Amendments and Reauthorization Act (SARA) of 1986, is releasing the proposed plan for remedial action at the United Nuclear Corporation (UNC) Disposal Site located at the DOE Oak Ridge Operations (ORO) Y-12 Plant, Oak Ridge, Tennessee. The purpose of this document is to present and solicit for comment to the public and all interested parties the preferred plan'' to remediate the UNC Disposal Site. However, comments on all alternatives are invited.
Date: March 1, 1991
Partner: UNT Libraries Government Documents Department

Method of calculation of heat generation rates for DWPF glass

Description: The Waste Acceptance Preliminary Specifications (WAPS) require estimates of the heat generation rate of DWPF waste glasses. Estimates of the heat generation rates of projected glass compositions are to be reported in the Waste Form Qualification Report. Similar estimates for actual production glasses are to be reported in the Production Records. In this report, a method of calculating the heat generation rate from the radionuclide inventory is provided. Application of the method to the DWPF Design-Basis glass indicates that the heat generation rate can be accurately estimated from the Sr-90, Y-90, Cs-137, Ba-137m, and Pu-238 contents alone.
Date: March 17, 1992
Creator: Plodinec, M.J.
Partner: UNT Libraries Government Documents Department

[beta][sup +] decay and cosmic-ray half-life of [sup 54]Mn

Description: We performed a search for the [beta][sup +] branch of [sup 54]Mn decay. As a cosmic ray, [sup 54]Mn, deprived of its atomic electrons, can decay only via [beta][sup +] and [beta][sup [minus]] decay, with a half-life of the order of 10[sup 6] yr. This turns [sup 54] Mn into a suitable cosmic chronometer for the study of cosmic-ray confinement times. We searched for coincident back-to-back 511-keV [gamma]-rays using two germanium detectors inside a Nal(Tl) annulus. An upper limit of 2[times]10[sup [minus]8] was found for the [beta][sup +] decay branch, corresponding to a lower limit of 13.7 for the log ft value.
Date: March 29, 1993
Creator: da Cruz, M.T.F.; Norman, E.B.; Chan, Y.D.; Garcia, A.; Larimer, R.M.; Lesko, K.T. et al.
Partner: UNT Libraries Government Documents Department

Thick-target yields of iodine isotopes from proton interactions in Te, and the double-[beta] decay of [sup 128,130]Te

Description: We report thick-target yields of [sup 126,128,130]I from the bombardment of natural Te targets with 15-, 30-, 45- and 50-MeV protons, together with the iodine production cross sections for 1.85- and 5.0-GeV protons. With these data, we have estimated the relative cosmic-ray induced production of [sup 126]Xe, [sup 128]Xe and [sup 13O]Xe in Te ores. These quantities affect the ratio of double-[beta] decay half-lives of [sup 13O]Te and [sup 128]Te. A revised correction of cosmic-ray induced xenon can change the half-life ratio by as much as 10%, from (3.52[plus minus]0.11) [times] 10[sup [minus]4] to (3.88[plus minus]0.14) [times] 10[sup [minus]4].
Date: March 29, 1993
Creator: da Cruz, M.T.F.; Chan, Y.D.; Garcia, A.; Larimer, R.M.; Lesko, K.T.; Norman, E.B. et al.
Partner: UNT Libraries Government Documents Department

Nuclear structure studies utilizing LAMPF. Annual progress report. [Summaries of research activities at Idaho National Engineering Laboratory]

Description: This report describes progress during FY-1975 on the study of the decay properties of selected neutron-deficient nuclides produced by proton-induced spallation reactions in the Clinton P. Anderson Meson Physics Facility (LAMPF) at LASL. These studies include the decay of /sup 128/Ba (2.4 d), /sup 128/Cs (3.9 min), /sup 131/Ba (11.7 d), /sup 134/Ce (75.9 h), /sup 134/La (6.67 min), and /sup 151/Tb (17.6 h), as well as half-life measurements of /sup 134/La and /sup 132/-/sup 135/Ce. In order to carry out studies of the longer-lived parents /sup 128/Ba and /sup 134/Ce, chemical separation techniques were developed to continuously remove the shorter-lived daughters /sup 128/Cs and /sup 134/La. All samples were isotope separated at INEL. In addition to these studies, the progress reported includes the development of measurement techniques necessary for planned future programmatic efforts. (auth)
Date: March 1, 1976
Creator: Reich, C. W.; Greenwood, R. C.; Helmer, R. G.; Gehrke, R. J. & Heath, R. L.
Partner: UNT Libraries Government Documents Department

New limit on the neutrinoless double beta decay of /sup 100/Mo

Description: A search for the neutrinoless double beta decay of /sup 100/Mo was conducted using thin Mo films and solid state Si detectors. The experiment has collected 3500 hours of data operating underground in a deep silver mine (3290 M.W.E.). Only one event was found to be consistent with neutrinoless double beta decay. Using this one event, a limit of greater than or equal to 1 x 10/sup 22/ years (1 sigma) is set on the /sup 100/Mo half-life. This is approximately five times larger than the best previous /sup 100/Mo limit.
Date: March 1, 1988
Creator: Krivicich, J. M.
Partner: UNT Libraries Government Documents Department

Environmental monitoring report on radiological status of the ground water beneath the Hanford site, January--December 1974

Description: Evaluation of ..beta../sub t/, /sup 3/H and NO/sub 3//sup -/ concentrations measured in well water sampled near the surface of the unconfined ground water during 1974 shows that zones of contamination extend in an easterly to south-easterly direction from 200-E Area, as has been observed in the past. Tritium and NO/sub 3//sup -/ ion concentrations above background were found along the Columbia River in the vicinity of the 100 Areas. A low ground-water mound showing uranium and nitrate ion concentrations above background continues to be observed in the 300 Area. Gross beta activity in the ground water beneath the 100 Areas was detectable only at the 100-N Area from effluent discharged to the 1301-N crib. A number of radionuclides, such as /sup 106/Ru, /sup 60/Co, /sup 129/I, /sup 137/Cs and /sup 90/Sr, occur at various locations and are detectable in very low concentrations in the unconfined ground water external to the 200 Areas. In most cases, concentrations are several orders of magnitude below applicable CG's and are so close to the detection limit as to cast doubt of their existence based on a single analysis. Only in and adjacent to the 200 Areas does any radionuclide that was analyzed in CY-1974 occur in concentrations greater than 10 percent of the applicable CG for uncontrolled water use. Nitrate ion concentrations greater than 100 percent of the Public Health Service (PHS) recommended drinking water standard of 45 mg/l continued to be observed in the ground water adjacent to the 200 Areas; in the vicinity of the 100-F and 300 Areas; and in the east-central part of the Hanford site (Wells 20-20, 26-15, and 32-22). Ground water from these zones is not consumed by human beings or other animals.
Date: March 1, 1976
Creator: Raymond, J. R.; Myers, D. A.; Fix, J. J.; McGhan, V. L. & Schrotke, P. M.
Partner: UNT Libraries Government Documents Department

Using local momentum to disentangle angular distributions. [Optical model, DWBA]

Description: Optical model elastic and DWBA transfer angular distributions are studied by isolating their positive and negative deflection angle components. The local angular momentum of these amplitudes allows isolation of the regions of angular momentum space that are contributing to the different angular regions of the cross sections. This information can be employed to isolate features of the cross sections arising from orbiting, reflection, Coulomb rainbows, nuclear rainbows, Regge poles, etc. Specifically it is shown that the inner contribution to typical heavy-ion forward-angle elastic scattering is in the shadow of the nuclear rainbow and further that transfer angular distributions contain separate inner and outer contributions. Before discussing results, the idea of a ''local momentum'' is introduced and the decomposition of angular distributions into their positive and negative deflection angle components is briefly described. Results are shown for the reaction /sup 60/Ni(/sup 13/C,/sup 12/C)/sup 61/Ni at E = 60.8 MeV and for the elastic scattering of /sup 13/C on /sup 60/Ni at the same incident energy. (SDF)
Date: March 1, 1976
Creator: Fuller, R. C. & Moffa, P. J.
Partner: UNT Libraries Government Documents Department

Sequim Marine Research Laboratory routine environmental measurements during CY-1978. [Monitoring for laboratory-related radioactivity and pollutants in environment]

Description: Environmental data collected during 1978 in the vicinity of the Marine Research Laboratory show continued compliance with all applicable state and federal regulations and furthermore show no detectable change from conditions that existed in previous years. Samples collected for radiological analysis included soil, drinking water, bay water, clams, and seaweed. Radiation dose rates at 1 meter aboveground were also measured.
Date: March 1, 1979
Creator: Houston, J.R. & Blumer, P.J.
Partner: UNT Libraries Government Documents Department

Pacific Northwest Laboratory monthly report to the Nuclear Research and Applications Division, for February 1976. [/sup 90/SrF/sub 2/]

Description: At Hanford, strontium is separated from the high-level waste, then converted to the fluoride, and doubly encapsulated in small, high-integrity containers for subsequent long-term storage. The fluoride conversion, encapsulation and storage take place in the Waste Encapsulation and Storage Facilities (WESF). This encapsulated strontium fluoride represents an economical source of /sup 90/Sr if the WESF capsule can be licensed for heat source applicatons under anticipated use conditions. The objectives of this program are to obtain the data needed to license /sup 90/SrF/sub 2/ heat sources and specifically the WESF /sup 90/SrF/sub 2/ capsules. The information needed for licensing can be divided into three general areas: (1) long-term SrF/sub 2/ compatibility data; (2) chemical and physical property data on /sup 90/SrF/sub 2/; and (3) capsule property data such as external corrosion resistance, crush strength, etc. The current program is designed to provide the required information.
Date: March 1, 1976
Creator: Fullam, H. T.
Partner: UNT Libraries Government Documents Department

Physical basis for large forward cross sections in /sup 60/Ni(/sup 18/O,/sup 16/O) reaction

Description: Experiments on the reaction /sup 60/Ni(/sup 18/O,/sup 16/O)/sup 62/Ni revealed an unexpectedly large forward cross section for production of the ground state, in contrast with an expected grazing peaked distribution. This has most recently been interpreted in terms of a surface transparent optical potential. In the inverse experiment, it is known that /sup 18/O is produced in its 2/sup +/ state with larger cross section than the ground state. This suggests that the above ground state reaction can also be produced with appreciable probability through the excitation of /sup 18/O in the incident channel, with a subsequent transfer of two neutrons to form the ground state of /sup 62/Ni. It is found that by including this process together with the direct transfer, the experimental data can be accounted for. The parameters of the optical potential employed are chosen so as to reproduce both the elastic and inelastic cross sections, and are of the normal strong absorbing type with no surface transparency. It is concluded that the projectile excitation is the physical process involved in the large forward cross section. In addition the interference of the direct and indirect processes can give rise to a minimum beyond the grazing peak followed by a secondary maximum, some indication of which can be found in the experiments on neighboring nuclei. The quantal deflection function is employed in a discussion of the S matrix and angular distribution emerging from this calculation and of the surface transparent potential parametrization of the effect. 5 figures, 1 table.
Date: March 1, 1976
Creator: Glendenning, N. K. & Wolschin, G.
Partner: UNT Libraries Government Documents Department

Stored energy of gamma-irradiated WIPP salt

Description: Samples of WIPP salt exposed at 363/sup 0/K to gamma radiation from a /sup 60/Co source were annealed at constant rates of heating in a differential scanning calorimeter in order to release the energy stored. Radiation doses were 2.2, 5.4, 8.2, 11 and 13 x 10/sup 9/ rad, and temperature scans were conducted from room temperature to 800/sup 0/K. The specific stored energy-dose relationship deduced from 80 K/min scans could be only approximately established due to the extreme variability of the specific energy in samples of a given dose. This variability probably results from unequal amounts of impurities in the 10 to 25 mg samples required for the calorimeter. The energy-dose relationship is best described empirically by lnQ/sub 0/(cal/g) = (-40.6 +- 2.6) + (1.84 +- 0.12) lnD(rad). Temperature scans of 10, 20, 40, and 80 K/min were performed to determine the activation energy E of the annealing process. For the four more highly dosed samples, E = 31.1 +- 5.6 kcal/mole. Based upon criteria established elsewhere, there appears to be no danger of the stored energy being released quickly in a nuclear waste repository of bedded salt, nor could serious consequences result from such a release by some unforeseen mechanism.
Date: March 1, 1980
Creator: Moss, M.
Partner: UNT Libraries Government Documents Department

Coal liquefaction process research quarterly report, October-December 1979

Description: This quarterly report summarizes the activities of Sandia's continuing program in coal liquefaction process research. The overall objectives are to: (1) provide a fundamental understanding of the chemistry of coal liquefaction; (2) determine the role of catalysts in coal liquefaction; and (3) determine the mechanism(s) of catalyst deactivation. The program is composed of three major projects: short-contact-time coal liquefaction, mineral effects, and catalyst studies. These projects are interdependent and overlap significantly.
Date: March 1, 1980
Creator: Bickel, T.C.; Curlee, R.M.; Granoff, B.; Stohl, F.V. & Thomas, M.G.
Partner: UNT Libraries Government Documents Department

Technical Division quarterly progress report, October 1--December 31, 1976

Description: The first in a series of quarterly progress reports on ERDA budgeted activities subcontracted to Allied Chemical Corporation at the Idaho National Engineering Laboratory is presented. The work is performed by the Technical Division and is divided into three subjects. Fuel cycle research and development includes fluidized-bed calcination and post treatment of commercial nuclear fuel process waste; the storage of fission product noble gas; the catalyzed reaction between NO/sub x/ and NH/sub 3/; the adsorption and storage of /sup 129/I; evaporation of radioactive wastes; the removal of actinides from commercial high-level waste; reprocessing and waste treatment of HTGR fuel; and studies on natural fission reactors. Special materials production covers long-term management of ICPP high-level waste; ICPP fuel process improvements; advanced graphite fuels reprocessing; buried pipeline transfer systems; and ICPP waste management assistance. Other projects supporting energy development include geothermal energy development; inplant source term measurements; burnup methods for FBR fuels; nuclear materials security; absolute thermal fission yield measurements; analytical support to LWBR program; research on analytical methods; and environmental iodine species behavior.
Date: March 1, 1977
Creator: Slansky, C. M. (ed.)
Partner: UNT Libraries Government Documents Department

Preliminary evaluation of the gaseous effluent sampling system of the 296-P-3 portable exhauster, BY-Tank Farm

Description: This evaluation of the 296-P-3 stack sampling system is part of a larger study, sponsored by ARHCO and conducted by Battelle-Northwest, of effluent airborne particulate sampling systems in ARHCO facilities. The 296-P-3 stack is similar to many portable exhauster units deployed in the tank farms. The objectives of this study are: Evaluate the compliance of the particulate sampling system with ARHCO's Interim Criteria for such systems by using sampling theory; make recommendations for corrective action which will lead to a particulate sampling system in compliance with the Interim Criteria; and the conclusions and recommendations are to be generally applicable to sampling systems of the same type as at the 296-P-3 stack. This study is considered preliminary because no experiments have been conducted to verify the sampling system's performance. The following report includes a brief summary, a detailed description and evaluation of the sampling system, conclusions and recommendations for corrective action. The appendices contain a copy of the Interim Criteria, the ARHCO Emergency Procedure regarding radioactive gaseous discharges from this facility and calculations.
Date: March 1, 1977
Creator: Glissmeyer, J.A. & Schwendiman, L.C.
Partner: UNT Libraries Government Documents Department

Atmospheric radionuclide concentrations measured by Pacific Northwest Laboratory since 1961

Description: The atmospheric concentrations of a wide spectrum of radionuclides produced by nuclear weapons, nuclear reactors, cosmic rays, radon and thoron decay and the SNAP-9A burn-up ([sup 238]Pu) have been measured at Richland, Washington, since 1961; at Barrow, Alaska, since 1964; and at other stations for shorter periods of time. There has been considerable concern over the health hazard presented by these radionuclides, but it has also been recognized that atmospheric mixing and deposition rates can be determined from their measurement. Therefore, Pacific Northwest Laboratory began the continuous measurement of the atmospheric concentrations of a wide spectrum of radionuclides produced by nuclear weapons, nuclear reactors, cosmic rays, and radon and thoron decay. This report will discuss the concentrations of the longer-lived radionuclides (T 1/2 > 12 days). The concentrations of shorter-lived radionuclides measured following Chinese nuclear tests since 1972 are discussed in another report.
Date: March 1, 1981
Creator: Young, J.A. & Thomas, C.W.
Partner: UNT Libraries Government Documents Department

Iodine-131 releases from the Hanford Site, 1944--1947

Description: Detailed results of the Hanford Environmental Dose Reconstruction project (HEDR) iodine-131 release reconstruction are presented in this volume. Included are daily data on B, D, and F Plant, reactor operations from the P-Department Daily Reports (General Electric Company 1947). Tables of B and T Plant material processed from the three principal sources on separations plant operations: The Jaech report (Jaech undated), the 200 Area Report (Acken and Bird 1945; Bird and Donihee 1945), and the Metal History Reports (General Electric Company 1946). A transcription of the Jaech report is also provided because it is computer-generated and is not readily readable in its original format. The iodine-131 release data are from the STRM model. Cut-by-cut release estimates are provided, along with daily, monthly, and yearly summations. These summations are based on the hourly release estimates. The hourly data are contained in a 28 megabyte electronic file. Interested individuals may request a copy.
Date: March 1, 1993
Creator: Heeb, C.M.
Partner: UNT Libraries Government Documents Department

Iodine-131 releases from the Hanford Site, 1944--1947

Description: Releases of fission product iodine-131 are calculated for the 1944 through 1947 period from the Hanford Reservation. Releases to the atmosphere were from the ventilation stacks of T and B separation plants. A reconstruction of daily separation plant operations forms the basis of the releases. The reconstruction traces the iodine-131 content of each fuel discharge from the B, D, and F Reactors to the dissolving step in the separation plants. Statistical computer modeling techniques are used to estimate hourly release histories based on sampling mathematical distribution functions that express the uncertainties in the source data and timing. The reported daily, monthly, and yearly estimates are averages and uncertainty ranges are based on 100 independent Monte Carlo realizations'' of the hourly release histories.
Date: March 1, 1993
Creator: Heeb, C.M.
Partner: UNT Libraries Government Documents Department

Natural repository analogue program. Progress report, July 1-September 30, 1981

Description: A report on the immobilization of uranium in the earth's crust has been completed. Techniques have been developed to do a comprehensive mass inventory of the Oklo reactor zones. These techniques were applied to a compilation of data from Oklo zones 2 and 3-4. The study shows large deficiencies of neodymium, ruthenium, and mass 99 elements (/sup 99/Tc or /sup 99/Ru) in the reactor zones. The extent of these deficiencies are correlated with the intensity of the nuclear reactions. Analyses of ores from the Key Lake uranium mineralization show that 60 to 70% of the radiogenic lead is missing from the ores.
Date: March 1, 1982
Creator: Curtis, D.B. (comp.)
Partner: UNT Libraries Government Documents Department

Defense waste processing facility precipitate hydrolysis process

Description: Sodium tetraphenylborate and sodium titanate are used to assist in the concentration of soluble radionuclide in the Savannah River Plant's high-level waste. In the Defense Waste Processing Facility, concentrated tetraphenylborate/sodium titanate slurry containing cesium-137, strontium-90 and traces of plutonium from the waste tank farm is hydrolyzed in the Salt Processing Cell forming organic and aqueous phases. The two phases are then separated and the organic phase is decontaminated for incineration outside the DWPF building. The aqueous phase, containing the radionuclides and less than 10% of the original organic, is blended with the insoluble radionuclides in the high-level waste sludge and is fed to the glass melter for vitrification into borosilicate glass. During the Savannah River Laboratory's development of this process, copper (II) was found to act as a catalyst during the hydrolysis reactions, which improved the organic removal and simplified the design of the reactor.
Date: March 1, 1986
Creator: Doherty, J P; Eibling, R E & Marek, J C
Partner: UNT Libraries Government Documents Department

Positron annihilation in solid and liquid Ni

Description: New techniques have been developed for the study of metals via positron annihilation which provide for the in-situ melting of the samples and subsequent measurements via Doppler broadening of positron-annihilation radiation. Here we report these metods currently in use at our laboratory; ion implantation of /sup 58/Co and the use of Al/sub 2/O/sub 3/ crucibles for in-situ melting followed by the decomposition of the Doppler-broadened spectrum into a parabolic and a Gaussian component. Our earliest results obtained for pure Ni in the polycrystalline solid and in the liquid state are compared. An interesting similarity is reported for the distributions of the high-momentum (Gaussian) component for positrons annihilating in vacancies at high temperatures and those annihilating in liquid Ni.
Date: March 1, 1982
Creator: Fluss, M.J.; Smedskjaer, L.C.; Chakraborty, B. & Chason, M.K.
Partner: UNT Libraries Government Documents Department

Nuclear medicine program progress report for quarter ending December 31, 1992

Description: We describe the synthesis of the cis- and trans-iodovinyl isomers of the new ORNL cholinergic-muscarinicreceptorligand, 1 -azabicyclo[2.2-2]oct-3-yl[alpha]-hydroxy-[alpha]-(1-iodo-l-propen-3-yl)-[alpha]-phenylacetate ( IQNP''). This agent is prepared in high radiochemical yield, and the racemic mixture shows high specificity and selectivity for the cerebral and myocardial receptors. Since two chiral centers are present in this molecule, it is important to evaluate the importance of the absolute configuration of the two centers on receptor specificity. The tributyltin substrates were carefully separated by column chromatography, converted to the iodine-125 analogues by iododestannylation, and evaluated in rats in vivo. While the E'' (trans) isomer cleared rapidly from the receptor-rich areas of rat brain, the Z'' (cis) isomer showed high uptake in these areas but also high concentration in the cerebellum. In contrast, the E,Z-isomeric mixture showed good uptake and retention in the receptor rich areas. Also described in this report is a description of neutron flux measurements in the hydraulic tube position at the ORNL High Flux Isotope Reactor (HFIR). Also during this period, samples of [l-125]- and [l-131]-labeled racemic IQNP'' were supplied through a collaborative program with the Brookhaven National Laboratory for high resolution autoradiographic studies in rat tissues.
Date: March 1, 1993
Creator: Knapp, F.F. Jr.; Ambrose, K.R.; Beets, A.L.; Callahan, A.P.; McPherson, D.W.; Mirzadeh, S. et al.
Partner: UNT Libraries Government Documents Department

Radioactive contamination in the environs of the Hanford Works for the period July, August, September 1948

Description: This report summarizes the radioactive contamination measured at the Hanford Works and vicinity for the quarter July, August, and September 1948. Topics discussed are: meteorology; airborne contamination and contamination of the Columbia River; vegetation; drinking water; and in Hanford Wastes.
Date: March 10, 1949
Creator: Singlevich, W.
Partner: UNT Libraries Government Documents Department