The detonation of a radiological dispersion device or other radiological incidents could result in widespread releases of radioactive materials and intakes of radionuclides by affected individuals. Transportable radiation monitoring instruments could be used to measure radiation from gamma-emitting radionuclides in the body for triaging individuals and assigning priorities to their bioassay samples for in vitro assessments. The present study derived sets of calibration factors for four instruments: the Ludlum Model 44-2 gamma scintillator, a survey meter containing a 2.54 × 2.54-cm NaI(Tl) crystal; the Captus 3000 thyroid uptake probe, which contains a 5.08 × 5.08-cm NaI(Tl) crystal; the Transportable Portal Monitor Model TPM-903B, which contains two 3.81 × 7.62 × 182.9-cm polyvinyltoluene plastic scintillators; and a generic instrument, such as an ionization chamber, that measures exposure rates. The calibration factors enable these instruments to be used for assessing inhaled or ingested intakes of any of four radionuclides: 60Co, 131I, 137Cs, and 192Ir. The derivations used biokinetic models embodied in the DCAL computer software system developed by the Oak Ridge National Laboratory and Monte Carlo simulations using the MCNPX radiation transport code. The three physical instruments were represented by MCNP models that were developed previously. The affected individuals comprised children of five ages who were represented by the revised Oak Ridge National Laboratory pediatric phantoms, and adult men and adult women represented by the Adult Reference Computational Phantoms described in Publication 110 of the International Commission on Radiological Protection. These calibration factors can be used to calculate intakes; the intakes can be converted to committed doses by the use of tabulated dose coefficients. These calibration factors also constitute input data to the ICAT computer program, an interactive Microsoft Windows-based software package that estimates intakes of radionuclides and cumulative and committed effective doses, based on measurements made with these instruments. This program constitutes a convenient tool for assessing intakes and doses without consulting tabulated calibration factors and dose coefficients.
The Environmental Protection Agency (EPA) has proposed national radionuclide air emission standards for a number of source categories. One of these standards applies to Nuclear Regulatory Commission Licensees and non-Department of Energy facilities having the potential to release radionuclides to the atmosphere. Approximately 6000 facilities are subject to the standard, which limits the effective whole-body dose commitment to the maximally exposed individual from radionuclide releases to the atmosphere. A computer program to assist the regulated community in determining compliance has been developed by the EPA's Office of Radiation Programs. The computer program COMPLY calculates the dose to an individual residing outside the facility. The program considers dose from inhalation, ingestion of contaminated food, air immersion, and ground deposition. It is based on models developed by the National Council on Radiation Protection and Measurements (NCRP). Compliance procedures provided in COMPLY are designed to reduce the burden on the regulated community. The approach begins with simple-to-use methods that are very conservative in determining compliance. The methods become progressively less conservative but more complicated at succeeding levels. Each higher level requires the input of site-specific information, but allows a more realistic estimate of dose. This paper describes the COMPLY program, and provides estimates of the work required and the degree of conservatism in the dose computed at each level.
Under contract to the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. The characterization of Class-A low-level waste is based primarily on information contained in the Manifest Information Management System (MIMS), an electronic database compiled by the National Low-Level Waste Management Program. The Program is managed by EG&G Idaho, Inc. for the Department of Energy. Supplementary sources of information include reports and studies conducted under the auspices of the Nuclear Regulatory Commission, Department of Energy, regional low-level waste Compacts and unaffiliated States, and trade organizations. The database characterizes low-level waste shipped for disposal from 1986 to 1990. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information. iii VOLUME 5 APPENDIX Appendix F presents additional information for the Executive Summary (Vol. i) and Main Report (Vol. 2 and 3). Contents Appendix Paqe F Waste Radionuclide Concentrations by Compact Regions and States -Shipment-level Analyses: All Disposal Sites and Non-Brokered Wastes Aggregate Practices 1986-1990
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