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Evaluation of concentrations of hazardous components to support removal of the Tank 48 thermowell

Description: In support of start-up activities for the In Tank Precipitation (ITP) process, a thermowell is scheduled to be removed from Tank 48. Disposal of the thermowell in the Solid Waste Disposal Facility (SWDF) requires manifesting the quantities of several radioisotopes and, equally important, declaring that the waste package is nonhazardous. Sampling of the waste in the package (i.e., the thermowell) to determine quantities of hazardous materials or to perform a Toxicity Characteristic Leaching Proc… more
Date: September 28, 1994
Creator: Georgeton, G. K.
Partner: UNT Libraries Government Documents Department
open access

Temperature and dose dependence of metal colloid production in alpha-irradiated CaF{sub 2}

Description: Single crystals of CaF{sub 2} were irradiated with 5.8 MeV alpha particles from a {sup 244}Cm source. The absorbance spectra were recorded as a function of dose and temperature. At low doses, the absorbance from the colloid band increased with dose to saturation values that changed with temperature. The colloid band exhibited a sharp increase in rate of growth over a narrow temperature range with a peak at 150{degrees}C. The intensity of the colloid band after a dose of 1.4 {times} 1016 a/cm{su… more
Date: November 1, 1994
Creator: Weber, W. J.; Exarhos, G. J. & Wang, L. M.
Partner: UNT Libraries Government Documents Department
open access

Expression of cytoskeletal and matrix genes following exposure to ionizing radiation: Dose-rate effects and protein synthesis requirements

Description: Experiments were designed to examine the effects Of radiation dose-rate and of the protein synthesis inhibitor cycloheximide on expression of cytoskeletal elements ({gamma}- and {beta}-actin and {alpha}-tubulin) and matrix elements (fibronectin) in Syrian hamster embryo cells. Past work from our laboratory had already demonstrated optimum time points and doses for examination of radiation effects on accumulation of specific transcripts. Our results here demonstrated little effect of dose-rate f… more
Date: May 1, 1994
Creator: Woloschak, G. E.; Felcher, P. & Chang-Liu, Chin-Mei
Partner: UNT Libraries Government Documents Department
open access

Operational dose rate visualization techniques

Description: The analysis of the gamma ray dose rate in the vicinity of a radiation source can be greatly aided by the use of recent state-of-the-art visualization techniques. The method involves calculating dose rates at thousands of locations within a complex geometry system. This information is then processed to create contour plots of the dose rate. Additionally, when these contour plots are created, animations can be created that dynamically display the dose rate as the shields or sources are moved.
Date: January 1, 1994
Creator: Schwarz, R. A.; Morford, R. J.; Carter, L. L.; Jones, G. B. & Greenborg, J.
Partner: UNT Libraries Government Documents Department
open access

Measured thermal and fast neutron fluence rates ATR Cycle 101-B, October 11, 1993--November 27, 1993

Description: This report contains the thermal (2200 m/s) and fast (E>lMeV) neutron fluence rate data for ATR Cycle 101-B which were measured by the Radiation Measurements Laboratory (RML) as requested by the Power Reactor Programs (ATR Experiments) Radiation Measurements Work Order. This report contains fluence rate values corresponding to the particular elevations (relative to the 80 ft. core elevation) where the measurements were taken. The data in this report consists of (1) a table of the ATR power hist… more
Date: January 1, 1994
Creator: Murray, R. K. & Rogers, J. W.
Partner: UNT Libraries Government Documents Department
open access

Vanadium recycling for fusion reactors

Description: Very stringent purity specifications must be applied to low activation vanadium alloys, in order to meet recycling goals requiring low residual dose rates after 50--100 years. Methods of vanadium production and purification which might meet these limits are described. Following a suitable cooling period after their use, the vanadium alloy components can be melted in a controlled atmosphere to remove volatile radioisotopes. The aim of the melting and decontamination process will be the achieveme… more
Date: April 1, 1994
Creator: Dolan, T. J. & Butterworth, G. J.
Partner: UNT Libraries Government Documents Department
open access

Chernobyl Studies Project - working group 7.0 environmental transport and health effects. Progress report, October 1993--January 1994

Description: The DOE-funded Chernobyl Studies Project was begun as part of a cooperative agreement between the US and the former USSR, (quote) To develop jointly methods to project rapidly the health effects of any future reactor accident (quote). Most of the initial tasks for this project are completed or near completion. The focus has now turned primarily to the issue of health effects from the Chernobyl accident. Currently, we are extensively engaged in case-control and cohort studies of thyroid diseases… more
Date: March 1, 1994
Creator: Hendrickson, S. M.
Partner: UNT Libraries Government Documents Department
open access

Chernobyl Studies Project. Working Group 7.0, environmental transport and health effects. Progress report, February 1994

Description: The focus of the Chernobyl Studies Project has now turned to the issue of health effects from the Chernobyl accident. Currently, we are involved in and making progress on the case-control and co-hort studies of thyroid diseases among Belarussian children. Dosimetric aspects are a fundamental part of these studies. We are working to implement similar studies in Ukraine. A major part of the effort of these projects is supporting these studies, both by providing methods and applications of dose re… more
Date: April 1, 1994
Creator: Hendrickson, S. M.
Partner: UNT Libraries Government Documents Department
open access

Update of HB-line consequences based on new meteorological and population databases in AXAIR89Q

Description: Additional analyses and upgrading of the Safety Analysis Report (SAR) and Justification for Continued Operation (JCO) is needed for an Environmental Assessment (EA) currently being prepared for HB-Line. Since the JCO and SAR do not include population doses for two accidents; a propagated fire and a ground level release for an earthquake, this analysis will provide these doses. Population distribution information has been updated to 1992. This analysis will analyze the onsite worker at a distanc… more
Date: March 1, 1994
Creator: DelGenio, M. E.
Partner: UNT Libraries Government Documents Department
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Radiation effects in polymers for plastic scintillation detectors

Description: Radiation damage studies were performed on polystyrene and poly(vinyltoluene) samples containing different concentrations of either an antioxidant (A O-2) or a plasticizer (PP-4). In addition, parallel studies were carried out utilizing samples of these polymers prepared in the presence of cross-linking agents such as NPG, HDA, and DVB. The samples were irradiated using a {sup 60} Co source to total doses of 1 and 10 Mrad, at a dose rate of approximately 1 Mrad/h. Transmittance measurements wer… more
Date: April 20, 1994
Creator: Pla-Dalmau, A.; Bross, A. D.; Hurlbut, C. R. & Moser, S. W.
Partner: UNT Libraries Government Documents Department
open access

Dose rate estimates from irradiated light-water-reactor fuel assemblies in air

Description: It is generally considered that irradiated spent fuel is so radioactive (self-protecting) that it can only be moved and processed with specialized equipment and facilities. However, a small, possibly subnational, group acting in secret with no concern for the environment (other than the reduction of signatures) and willing to incur substantial but not lethal radiation doses, could obtain plutonium by stealing and processing irradiated spent fuel that has cooled for several years. In this paper,… more
Date: January 31, 1994
Creator: Lloyd, W. R.; Sheaffer, M. K. & Sutcliffe, W. G.
Partner: UNT Libraries Government Documents Department
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Structural activation calculations due to proton beam loss in the APT accelerator design

Description: For the new, high-power accelerators currently being designed, the amount of activation of the accelerator structure has become an important issue. To quantify this activation, a methodology was utilized that coupled transport and depletion codes to obtain dose rate estimates at several locations near the accelerator. This research focused on the 20 and 100 MeV sections of the Bridge-Coupled Drift Tube Linear Accelerator. The peak dose rate was found to be approximately 6 mR/hr in the 100 MeV s… more
Date: August 1, 1994
Creator: Lee, S. K.; Beard, C. A.; Wilson, W. B.; Daemen, L. L.; Liska, D. J.; Waters, L. S. et al.
Partner: UNT Libraries Government Documents Department
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Construction and operation of an improved radiation calibration facility at Brookhaven National Laboratory. Environmental assessment

Description: Calibration of instruments used to detect and measure ionizing radiation has been conducted over the last 20 years at Brookhaven National Laboratory`s (BNL) Radiation Calibration Facility, Building 348. Growth of research facilities, projects in progress, and more stringent Department of Energy (DOE) orders which involve exposure to nuclear radiation have placed substantial burdens on the existing radiation calibration facility. The facility currently does not meet the requirements of DOE Order… more
Date: October 1, 1994
Partner: UNT Libraries Government Documents Department
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Determination of iodine to compliment mass spectrometric measurements

Description: The dose of iodine-129 to facility personnel and the general public as a result of past, present, and future activities at DOE sites is of continuing interest, WINCO received about 160 samples annually in a variety of natural matrices, including snow, milk, thyroid tissue, and sagebrush, in which iodine-129 is determined in order to evaluate this dose, Currently, total iodine and the isotopic ratio of iodine-127 to iodine-129 are determined by mass spectrometry. These two measurements determine… more
Date: November 1, 1994
Creator: Hohorst, F.A.
Partner: UNT Libraries Government Documents Department
open access

Estimates of bias and uncertainty in recorded external dose

Description: A study is underway to develop an approach to quantify bias and uncertainty in recorded dose estimates for workers at the Hanford Site based on personnel dosimeter results. This paper focuses on selected experimental studies conducted to better define response characteristics of Hanford dosimeters. The study is more extensive than the experimental studies presented in this paper and includes detailed consideration and evaluation of other sources of bias and uncertainty. Hanford worker dose esti… more
Date: October 1, 1994
Creator: Fix, J. J.; Gilbert, E. S. & Baumgartner, W. V.
Partner: UNT Libraries Government Documents Department
open access

Dose rate analysis for Tank 101 AZ (Project W151)

Description: This document describes the expected dose rates for modification to tank 101 AZ including modifications to the steam coil, mixer pump, and temperature probes. The thrust of the effort is to determine dose rates from: modification of a steam coil and caisson; the installation of mixer pumps; the installation of temperature probes; and estimates of dose rates that will be encountered while making these changes. Because the dose rates for all of these configurations depend upon the photon source w… more
Date: November 1, 1994
Creator: Schwarz, R. A.; Hillesland, K. E. & Carter, L. L.
Partner: UNT Libraries Government Documents Department
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Thorium-232 in human tissues: Metabolic parameters and radiation doses

Description: Higher than environmental levels of {sup 232}Th have been found in autopsy samples of lungs and other organs from four former employees of a Th refinery. Working periods of the subjects ranged from 3 to 24 years, and times from end of work to death ranged from 6 to 31 years. Concentrations of {sup 232}Th in these samples and in tissues from two cases of non-occupational exposure were examined for compatibility with dosimetric models in Publication 30 of the International Commission on Radiologi… more
Date: September 1, 1994
Creator: Stehney, A. F.
Partner: UNT Libraries Government Documents Department
open access

An approximate algorithm for the flux from a rectangular volume source

Description: An exact semi-analytic formula for the flux from a rectangular surface source with a slab shield has been derived and the required function table has been calculated. This formula is the basis for an algorithm which gives a good approximation for the flux from a rectangular volume source. No other hand calculation method for this source geometry is available in the literature.
Date: November 9, 1994
Creator: Wallace, O. J.
Partner: UNT Libraries Government Documents Department
open access

Increasing the retained dose by plasma immersion ion implantation and deposition

Description: The retained dose of ions can be increased by Plasma Immersion Ion Implantation and Deposition (PIIID). A substrate is immersed in a metal or carbon plasma and a negative repetitively pulsed bias voltage is applied. During the pulses, an electric sheath is formed around the substrate and ions are accelerated through the sheath and implanted into the substrate. Direct and recoil ion implantation and sputtering take place during the pulses whereas low-energy deposition occurs between the pulses. … more
Date: July 22, 1994
Creator: Anders, A.; Anders, S.; Brown, I. G. & Yu, Kin M.
Partner: UNT Libraries Government Documents Department
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Gas bremsstrahlung and associated photon-neutron shielding calculations for electron storage rings

Description: The EGS4 electron-photon Monte Carlo code has been used to study the characteristics of the bremsstrahlung x-rays generated from the interaction of circulating electrons with the residual gas in accelerator storage rings. Gas bremsstrahlung dose rates are given for various opening angles as a function of the electron beam energy ranging from 0.5--10 GeV. Photon and neutron dose rates, generated from various devices struck by gas bremsstrahlung in a synchrotron radiation beamline, are also prese… more
Date: June 1, 1994
Creator: Liu, J. C.; Nelson, W. R. & Kase, K. R.
Partner: UNT Libraries Government Documents Department
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Development of the town data base: Estimates of exposure rates and times of fallout arrival near the Nevada Test Site

Description: As part of the U.S. Department of Energy`s Off-Site Radiation Exposure Review Project, the time of fallout arrival and the H+12 exposure rate were estimated for populated locations in Arizona, California, Nevada, and Utah that were affected by fallout from one or more nuclear tests at the Nevada Test Site. Estimates of exposure rate were derived from measured values recorded before and after each test by fallout monitors in the field. The estimate for a given location was obtained by retrieving… more
Date: September 1, 1994
Creator: Thompson, C. B.; McArthur, R. D. & Hutchinson, S. W.
Partner: UNT Libraries Government Documents Department
open access

Regulatory Analysis on Criteria for the Release of Patients Administered Radioactive Material

Description: The Nuclear Regulatory Commission (NRC) has received two petitions to amend its regulations in 10 CFR Parts 20 and 35 as they apply to doses received by members of the public exposed to patients released from a hospital after they have been administered radioactive material. While the two petitions are not identical they both request that the NRC establish a dose limit of 5 millisieverts (0.5 rem) per year for individuals exposed to patients who have been administered radioactive materials. Thi… more
Date: May 1, 1994
Creator: Schneider, S.; McGuire, S.A.; Behling, U.H.; Behling, K. & Goldin, D.
Partner: UNT Libraries Government Documents Department
open access

Activation of the liquid helium contamination during its passage in the Collider ring

Description: Radioactivation of possible contamination of the liquid helium trapped in the arcs of the Collider ring of the Superconducting Super Collider and transported by the liquid helium is estimated. This estimation is used to calculate the dose rate on the filter of the refrigerator plant located at the top of the shaft.
Date: January 1, 1994
Creator: Lopez, G.
Partner: UNT Libraries Government Documents Department
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