[en] The computer facility of the ANL Chemistry Division is described. A central facility providing all real-time support, the system provides each on-line experimentalist with all the advantages of a moderate-sized computer while also providing the isolation enjoyed by individually dedicated minicomputer systems. The system contains 56K works of core, 75 Mbytes of disk storage, an on-line plotter, two nine-track tape drives, high-speed line printer, card reader, card punch, and paper tape reader--punch. The 24 on-line experiments using the system are tabulated. (1 table) (U.S.)

No abstract available

[en] This paper presents information on the costs of nuclear waste management and on the impacts of those costs on the price of power and on the capital and labor markets. It is assumed that the LWR would be the sole commercial reactor used through the year 2000. Two fuel cycle options are considered: the throwaway mode (spent fuel is waste), and the full recycle for comparison. Total costs are calculated for all facilities needed to store, package, and reposit all the spent fuel through the lifetime of 380 GW capacity installed by 2000 and operating for 30 y. The economic impact is: the price of power produced by the reactors would be increased by 1.4%; the capital for nuclear plants would apply to waste management; the average annual labor effort needed over the next 50 to 75 years is 3000 to 5000 man years; and the unit cost of spent fuel disposal is $129/kg ($119/kg for full recycle). 7 tables

[en] The Uranium Dispersion and Dosimetry (UDAD) Code provides estimates of potential radiation exposure to individuals and to the general population in the vicinity of a uranium processing facility. The UDAD Code incorporates the radiation dose from the airborne release of radioactive materials, and includes dosimetry of inhalation, ingestion, and external exposures. The removal of raioactive particles from a contaminated area by wind action is estimated, atmospheric concentrations of radioactivity from specific sources are calculated, and source depletion as a result of deposition, fallout, and ingrowth of radon daughters are included in a sector-averaged Gaussian plume dispersion model. The average air concentration at any given receptor location is assumed to be constant during each annual release period, but to increase from year to year because of resuspension. Surface contamination and deposition velocity are estimated. Calculation of the inhalation dose and dose rate to an individual is based on the ICRP Task Group Lung Model. Estimates of the dose to the bronchial epithelium of the lung from inhalation of radon and its short-lived daughters are calculated based on a dose conversion factor from the BEIR report. External radiation exposure includes radiation from airborne radionuclides and exposure to radiation from contaminated ground. Terrestrial food pathways include vegetation, meat, milk, poultry, and eggs. Internal dosimetry is based on ICRP recommendations. In addition, individual dose commitments, population dose commitments, and environmental dose commitments are computed. This code also may be applied to dispersion of any other pollutant

[en] Three methods were used to perform a sensitivity analysis of RESRAD code input parameters -- enhancement of RESRAD by the Gradient Enhanced Software System (GRESS) package, direct parameter perturbation, and graphic comparison. Evaluation of these methods indicated that (1) the enhancement of RESRAD by GRESS has limitations and should be used cautiously, (2) direct parameter perturbation is tedious to implement, and (3) the graphics capability of RESRAD 4.0 is the most direct and convenient method for performing sensitivity analyses. This report describes procedures for implementing these methods and presents a comparison of results. 3 refs., 9 figs., 8 tabs

No abstract available

[en] The Uranium Dispersion and Dosimetry (UDAD) Code (Momeni, Yuan, and Zielen 1979) was developed to facilitate the prediction of potential radiation doses to individuals and populations in the vicinity of uranium processing facilities. The first step in these predictions is calculation of the airborne concentrations of radionuclides released during a routine industrial operation. In spite of efforts to provide flexibility for incorporating site-specific input values, the UDAD code prediction of airborne concentrations is subject to both theoretical and analytical uncertainties

[en] This document briefly describes the uses of the RESRAD computer code in calculating site-specific residual radioactive material guidelines and radiation dose-risk to an on-site individual (worker or resident) at a radioactively contaminated site. The adoption by the DOE in order 5400.5, pathway analysis methods, computer requirements, data display, the inclusion of chemical contaminants, benchmarking efforts, and supplemental information sources are all described

[en] This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material. It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating doses, risks, and guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. Two new pathways, radon inhalation and soil ingestion, have been added to RESRAD. Twenty-seven new radionuclides have also been added, and the cutoff half-life for associated radionuclides has been reduced to six months. Other major improvements to the RESRAD code include the ability to run sensitivity analyses, the addition of graphical output, user-specified dose factors, updated databases, an improved groundwater transport model, optional input of a groundwater concentration and a solubility constant, special models for tritium and carbon-14, calculation of cancer incidence risk, and the use of a mouse with menus

[en] A rapid and unique method for centering reflections on a computer-controlled, four-circle neutron diffractometer is presented. The method is based on numeric differentiation using the three-point form of Stirling's interpolation formula and its most outstanding features are the speed of operation and the high precision of the derived diffractometer coordinates. (Auth.)