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Plasma Separation Process: Betacell (BCELL) code: User's manual. [Bipolar barrier junction]

Description: The emergence of clearly defined applications for (small or large) amounts of long-life and reliable power sources has given the design and production of betavoltaic systems a new life. Moreover, because of the availability of the plasma separation program, (PSP) at TRW, it is now possible to separate the most desirable radioisotopes for betacell power generating devices. A computer code, named BCELL, has been developed to model the betavoltaic concept by utilizing the available up-to-date sour… more
Date: November 13, 1987
Creator: Taherzadeh, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The production of sulfate particles through the radiolytic oxidation of sulfur dioxide

Description: The production of hydroxyl radicals by the radiolytic decomposition of water vapor following alpha decay of {sup 222}Rn can be used to produce an ultrafine sulfuric acid aerosol in the presence of SO{sub 2}. In the past, the production of this aerosol appeared to have a limiting threshold in as much as sufficient conversion of SO{sub 2} to SO{sub 4} must be attained to achieve the concentration required for nucleation. This appeared to occur when the bulk average acidity reached an adequately h… more
Date: September 13, 1991
Creator: Karpen-Hayes, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Molten salt processing of mixed wastes with offgas condensation

Description: We are developing an advanced process for treatment of mixed wastes in molten salt media at temperatures of 700--1000{degrees}C. Waste destruction has been demonstrated in a single stage oxidation process, with destruction efficiencies above 99.9999% for many waste categories. The molten salt provides a heat transfer medium, prevents thermal surges, and functions as an in situ scrubber to transform the acid-gas forming components of the waste into neutral salts and immobilizes potentially fugit… more
Date: May 13, 1991
Creator: Cooper, J.F.; Brummond, W.; Celeste, J.; Farmer, J.; Hoenig, C.; Krikorian, O.H. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Use of AERIN code for determining internal doses of transuranic isotopes

Description: The AERIN computer code is a mathematical expression of the ICRP Lung Model. The code was developed at the Lawrence Livermore National Laboratory to compute the body organ burdens and absorbed radiation doses resulting from the inhalation of transuranic isotopes and to predict the amount of activity excreted in the urine and feces as a function of time. Over forty cases of internal exposure have been studied using the AERIN code. The code, as modified, has proven to be extremely versatile. The … more
Date: June 13, 1980
Creator: King, W.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Perspectives in the theory of nuclear collective motion

Description: This report discusses three different subjects. The first is the development of a generalized version of the VMI (variable moment of inertia) model that ties it to the original form of the IBM (interacting boson model) and provides a possibility of fitting vibrational spectra with generalized vibrational formulas. The second is a suggestion for fitting band crossing calculations of the phenomenological type more completely than has hitherto been done into the framework of the VMI method. The th… more
Date: March 13, 1980
Creator: Klein, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SEBREZ: an inertial-fusion-reactor concept

Description: The neutronic aspects of an inertial fusion reactor concept that relies on asymmetrical neutronic effects to enhance the tritium production in the breeding zones have been studied. We find that it is possible to obtain a tritium breeding ratio greater than 1.0 with a chamber configuration in which the breeding zones subtend only a fraction of the total solid angle. This is the origin of the name SEBREZ which stands for SEgregated BREeding Zones. It should be emphasized that this is not a reacto… more
Date: January 13, 1982
Creator: Meier, W. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Plutonium-aerosol emission rates and potential inhalation exposure during cleanup and treatment test at Area 11, Nevada Test Site

Description: A Cleanup and Treatment (CAT) test was conducted in 1981 at Area 11, Nevada Test Site. Its purpose was to evaluate the effectiveness of using a large truck-mounted vacuum cleaner similar to those used to clean paved streets for cleaning radiological contamination from the surface of desert soils. We found that four passes with the vehicle removed 97% of the alpha contamination and reduced resuspension by 99.3 to 99.7%. Potential exposure to cleanup workers was slight when compared to natural ba… more
Date: August 13, 1985
Creator: Shinn, J.H. & Homan, D.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of low /sup 60/Co dose rates on sister chromatid exchange incidence in the benthic worm. Neanthes arenaceodentata

Description: The usefulness of sister chromatid exchange (SCE) induction as a measure of low-level radiation effect was examined in a benthic marine worm, Neanthes arenaceodentata. Larvae were exposed to /sup 60/Co radiation for 12 to 24 h at total doses ranging from 0.5 to 309 R and at dose rates from 0.04 to 13 R/h. Animals exposed at intermediate dose rates (0.5, 0.6, 1.25, 2.0, and 2.5 R/h) had SCE frequencies per chromosome about twice that of those receiving no radiation (controls), whereas those expo… more
Date: October 13, 1981
Creator: Harrison, F.L. & Rice, D.W. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radionuclide Air Emission Report for 2007

Description: Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the U.S. Environmental Protection Agency (EPA) radioactive air emission regulations in Code of Federal Regulations (CFR) Title 40, Part 61, Subpart H (EPA 1989). The EPA regulates radionuclide emissions that may be released from stacks or vents on buildings where radionuclide production or use is authorized or that may be emitted as diffuse sources. In 2007, all Berkeley Lab sources were… more
Date: June 13, 2008
Creator: Wahl, Linnea & Wahl, Linnea
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DHS Regional Reachback: Rapid Expert Radiation Alarm Assistance.

Description: Following assessments that attacks with radiological and nuclear weapons are possible, detection system deployments are being supported at national and local levels. Detection systems include both, highly sensitive but non-discriminating detectors, as well as detectors and algorithms capable of distinguishing and identifying gamma rays by energy. The latter systems, usually handheld systems based on sodium iodide detectors, also provide analysis of the specific radionuclides present and are ref… more
Date: July 13, 2008
Creator: Bowerman, B.; Archer, D.; Young, J.; Monetti, M. & Savage, B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

PET Imaging of Adoptive Progenitor Cell Therapies

Description: Objectives. The overall objective of this application is to develop novel technologies for non-invasive imaging of adoptive stem cell-based therapies with positron emission tomography (PET) that would be applicable to human patients. To achieve this objective, stem cells will be genetically labeled with a PET-reporter gene and repetitively imaged to assess their distribution, migration, differentiation, and persistence using a radiolabeled reporter probe. This new imaging technology will be tes… more
Date: May 13, 2008
Creator: Gelovani, Juri G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Integrated system for production of neutronics and photonics calculational constants. Volume 15, Part E. Data testing results for the LLL Evaluated Nuclear Data Library (ENDL-78)

Description: The LLL Evaluated Nuclear Data Library (ENDL-78) was tested for validity by comparing calculated and experimental values of k/sub eff/ for 67 critical assemblies and emission neutron spectra for 22 spheres that were pulsed with 14-MeV neutrons. 22 figures, 5 tables.
Date: August 13, 1979
Creator: Howerton, Robert J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary evaluation of neutron capture cross sections for /sup 144/Sm, /sup 145/Sm and /sup 145/Pm

Description: We have made preliminary neutron-capture cross-section calculations of the Hauser-Feshbach type for the isotopes /sup 144/Sm, /sup 145/Sm, and /sup 145/Pm to investigate the production of radioactive /sup 145/Pm by neutron capture on the stable isotope /sup 144/Sm. The calculations were made for incident neutron energies from 2.5 MeV to about 1/sup -4/ or 10/sup -5/ MeV, wherever the first unbound resonance was estimated to occur in each case. At that energy, the calculated value was reduced by… more
Date: February 13, 1986
Creator: Gardner, D. G. & Gardner, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Estimating the dose from atmospheric releases of HT

Description: Measurements of uptake of tritium by humans and laboratory animals following exposure to tritiated hydrogen gas, HT, suggest that the radiotoxicity of HT is four orders of magnitude less than that of tritiated water, HTO. However, this analysis does not take into account the conversion of HT into HTO following release into the environment. Experimental releases of HT have demonstrated that HT release to the environment is converted to HTO by soil microorganisms. In this report two methods are u… more
Date: November 13, 1990
Creator: Murphy, C. E. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transfer factors for assessing the dose from radionuclides in agricultural products

Description: Transfer factors to predict the environmental transport of radionuclides through terrestrial foodchains to man were derived from the literature for radionuclides associated with the nuclear fuel cycle. We present updated transfer coefficients to predict the concentration of a radionuclide in cow's milk and other animal products and concentration factors (CF) to predict the concentration in a food or feed crop from that in soil. Where possible we note the variation of the transfer factor with ph… more
Date: June 13, 1979
Creator: Ng, Y.C.; Colsher, C.S. & Thompson, S.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of stream bed sediments of Four Mile Creek

Description: Until 1988, solutions containing nitric acid, odium hydroxide, low levels of radionuclides (mostly tritiated water) and some metals were discharged to unlined seepage basins at the F and H Areas of the Savannah River Site (SRS) as part of normal operations. The basins are now being closed according to the Resource Conservation and Recovery Act (RCA). As part of the closure, a Part B Post-Closure Care Permit is being prepared. The Part B permit requires information on contaminant concentrations … more
Date: August 13, 1990
Creator: Haselow, J.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Method of calculating test leakage rate for a spent fuel cask

Description: This report presents a method for calculating containment test leakage rates of radionuclides from an example spent fuel cask. Three releasable radioactive sources are considered: residual contamination in the cask cavity, crud on the fuel elements, and the radionuclides within the fuel rods. The ANSI N14.5 standard is used to calculate the test leakage rates from the maximum permissible releases determined from 10 CFR 71 containment requirements. 6 refs., 2 tabs.
Date: June 13, 1990
Creator: Fischer, L. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Quantities of uranium-235 buried in disposal boxes, 1985--1991

Description: IWT was asked by J. R. Schornhorst of NPSR to determine the distribution of the quantity of enriched uranium per disposal box (B-25) of the years 1985--1991 to provide input to an uptake of the E Area Safety Analysis. This information was considered important since the issue of criticality is an important concern in safety analyses. Information found in the COBRA data base shows no disposal containers exceeded 100 grams of U-235. The COBRA data base was queried in a two-step process. First a sh… more
Date: December 13, 1991
Creator: Cook, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An overview of copper-laser development for isotope separation

Description: We have developed a copper-laser pumped dye-laser system that addresses all of the requirements for atomic vapor laser isotope separation. The requirement for high average power for the laser system has led to the development of copper-laser chains with injection-locked oscillators and multihundred-watt amplifiers. By continuously operating the Laser Demonstration Facility, we gain valuable data for further upgrade and optimization.
Date: March 13, 1987
Creator: Warner, B.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Plutonium and uranium adsorption on monosodium titanate

Description: Adsorption of Pu and U onto monosodium titanate (MST) in alkaline salt solution was measured. Changes in MST particle size distribution do not significantly affect the loadings of actinides. Max loading of plutonium-239 is 0.68 wt% at 0.79 mg/L Pu, below the infinitely safe value of 0.80 wt%. Max loading of uranium-235 onto MST is 1.4 wt% at a concentration of 20.3 [plus minus] 2.0 mg/L U, slightly higher than the calculated infinitely safe limit of 1.2 wt%. Experimental data indicated there is… more
Date: August 13, 1992
Creator: Hobbs, D. T. & Walker, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Proceedings of the 2011 Monitoring Research Review: Ground-Based Nuclear Explosion Monitoring Technologies

Description: These proceedings contain papers prepared for the Monitoring Research Review 2011: Ground-Based Nuclear Explosion Monitoring Technologies, held 13-15 September, 2011 in Tucson, Arizona. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, Comprehensive Nuclear-Test-Ban … more
Date: September 13, 2011
Creator: Wetovsky, Marvin A.; Patterson, Eileen F. & Sandoval, Marisa N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2010

Description: Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants ([NESHAP]; U.S. Code of Federal Regulations, Title 40, Part 61, Subpart H) and Washington Administrative Code 246-247: Radiation Protection - Air Emissions. In these NESHAP assessments, potential unabated off-site doses were evaluated for emission locations at buildings that are part of the consolidated laboratory campu… more
Date: May 13, 2011
Creator: Ballinger, Marcel Y.; Gervais, Todd L. & Barnett, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Enrichment supply and technology outside the United States

Description: This is a review of foreign uranium enrichment capacity and uranium isotope separation technology, based on news items and articles in the public literature. Tables are included presenting capacity plans, growth, sales, research and development, etc. (DLC)
Date: January 13, 1977
Creator: Levin, S. A. & Blumkin, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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