TL;DR: This report describes work performed by Pacific Northwest Laboratory (PNL) for the Nuclear Regulatory Commission's program to determine safety and costs related to decommissioning nuclear fuel cycle facilities.
Abstract: This report describes work performed by Pacific Northwest Laboratory (PNL) for the Nuclear Regulatory Commission's program to determine safety and costs related to decommissioning nuclear fuel cycle facilities. Individual dose factors for the inhalation of radon and its daughter products are calculated for use in environmental dose assessments. The calculated committed dose equivalent factors for /sup 222/Rn and its daughters are tabulated for lungs, bronchi tract and other organs. An activity median aerodynamic diameter of 0.1 ..mu..m was used. The dose to an individual is calculated by multiplying the estimated intake from inhalation for a particular radionuclide by the corresponding dose factor. A working level month-to-dose conversion factor is calculated to be 1 rad/WLM to the epithelial tissue of the T-B region, assuming 100% daughter equilibrium and 10% free /sup 218/Po ions. This value is in reasonable agreement with recently reported values.
TL;DR: Seasonal changes in the committed effective dose equivalent rates are described and the contributions by the main foodstuffs, namely meat and milk, are assessed.
TL;DR: In this article, an updated summary of estimates of committed dose equivalent for radionuclides considered in three previous Oak Ridge National Laboratory (ORNL) reports is presented, which include contributions from specified source organs plus the systemic activity residing in the rest of the body; cross irradiation due to penetrating radiations has been incorporated into these estimates.
Abstract: This report presents internal radiation dose conversion factors for radionuclides of interest in environmental assessments of nuclear fuel cycles. This volume provides an updated summary of estimates of committed dose equivalent for radionuclides considered in three previous Oak Ridge National Laboratory (ORNL) reports. Intakes by inhalation and ingestion are considered. The International Commission on Radiological Protection (ICRP) Task Group Lung Model has been used to simulate the deposition and retention of particulate matter in the respiratory tract. Results corresponding to activity median aerodynamic diameters (AMAD) of 0.3, 1.0, and 5.0 ..mu..m are given. The gastorintestinal (GI) tract has been represented by a four-segment catenary model with exponential transfer of radioactivity from one segment to the next. Retention of radionuclides in systemic organs is characterized by linear combinations of decaying exponential functions, recommended in ICRP Publication 30. The first-year annual dose rate, maximum annual dose rate, and fifty-year dose commitment per microcurie intake of each radionuclide is given for selected target organs and the effective dose equivalent. These estimates include contributions from specified source organs plus the systemic activity residing in the rest of the body; cross irradiation due to penetrating radiations has been incorporated into these estimates. 15 references.
TL;DR: In this paper, a computer code has been developed that implements the recommendations of ICRP Committee 2 for computing limits for occupational exposure of radionuclides for computing specific effective energy, cumulated activity, and dose.
Abstract: A computer code has been developed that implements the recommendations of ICRP Committee 2 for computing limits for occupational exposure of radionuclides The purpose of this report is to describe the various modules of the computer code and to present a description of the methods and criteria used to compute the tables published in the Committee 2 report The computer code contains three modules of which: (1) one computes specific effective energy; (2) one calculates cumulated activity; and (3) one computes dose and the series of ICRP tables The description of the first two modules emphasizes the new ICRP Committee 2 recommendations in computing specific effective energy and cumulated activity For the third module, the complex criteria are discussed for calculating the tables of committed dose equivalent, weighted committed dose equivalents, annual limit of intake, and derived air concentration
TL;DR: The effective committed dose equivalent of a person 47 y old involved in this incident can hardly be used to quantify the risk, and therefore committed and annual dose equivalent systems were discussed in light of risk assessment.
Abstract: Intensive exposure of a product packaging operator to U product dust resulted in the uncontrolled inhalation of natural U. In-vivo counting yielded an estimate of about 40 mg of natural U initially deposited in the lung. An effective committed dose equivalent in the range of 67 mSv and 137 mSv was calculated to correspond to this lung contamination, using a single exponential lung clearance and the modified ICRP models, respectively. The effective committed dose equivalent of a person 47 y old involved in this incident can hardly be used to quantify the risk, and therefore committed and annual dose equivalent systems were discussed in light of risk assessment.