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SFACTOR: a computer code for calculating dose equivalent to a target organ per microcurie-day residence of a radionuclide in a source organ - supplementary report

Description: The purpose of this report is to describe revisions in the SFACTOR computer code and to provide useful documentation for that program. The SFACTOR computer code has been developed to implement current methodologies for computing the average dose equivalent rate S(X reverse arrow Y) to specified target organs in man due to 1 ..mu..Ci of a given radionuclide uniformly distributed in designated source orrgans. The SFACTOR methodology is largely based upon that of Snyder, however, it has been expan… more
Date: May 1, 1980
Creator: Dunning, D. E., Jr.; Pleasant, J. C. & Killough, G. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford environmental analytical methods (methods as of March 1990). Appendix A3-R

Description: Techniques in use at the Hanford Reservation as of March, 1990 for the analysis of liquids and radioactive effluents are described. Limitations and applications of the techniques are included. This report is Appendix A3-R.
Date: May 1, 1993
Creator: Goheen, S. C.; McCulloch, M. & Daniel, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The use of curium neutrons to verify plutonium in spent fuel and reprocessing wastes

Description: For safeguards verification of spent fuel, leached hulls, and reprocessing wastes, it is necessary to determine the plutonium content in these items. We have evaluated the use of passive neutron multiplicity counting to determine the plutonium content directly and also to measure the {sup 240}Pu/{sup 244}Cm ratio for the indirect verification of the plutonium. Neutron multiplicity counting of the singles, doubles, and triples neutrons has been evaluated for measuring {sup 240}Pu, {sup 244}Cm, a… more
Date: May 1, 1994
Creator: Miura, N. & Menlove, H. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Estimation of Ni{sup 63}, Pu{sup 241}, Pu{sup 242} and Am{sup 243} from Co{sup 60}, Pu{sup 239}, and Cm{sup 244} activities in groundwater samples

Description: The Part B Permit for F&H Seepage Basins calls for analysis of several constituents of concern in groundwater monitoring wells. Four of these analytes are the radionuclides Ni{sup 63}, Pu{sup 241}, Pu{sup 242}, and Am{sup 243}. These are currently not being analyzed due to their very difficult, tedious analytical schemes coupled with their relatively low activity values. This report demonstrates how the activity value for Ni{sup 63}, a week beta emitter, can be estimated from that of Co{sup 60}… more
Date: May 14, 1993
Creator: Holcomb, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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UNDERWATER ANALYSIS OF IRRADIATED REACTOR SLUGS FOR Co-60 AND OTHER RADIONUCLIDES AT THE SAVANNAH RIVER SITE

Description: Co-60 was produced in the Savannah River Site (SRS) reactors in the 1970s, and the irradiated cobalt reactor slugs were stored in a reactor basin at SRS. Since the activity rates of these slugs were not accurately known, assaying was required. A sodium iodide gamma detector was placed above a specially designed air collimator assembly, so that the slug was eight to nine feet from the detector and was shielded by the basin water. Also, 18 curium sampler slugs, used to produce Cm-244 from Pu-239,… more
Date: May 10, 2004
Creator: CASELLA, VITO
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effect of Internal Alpha Radiation on Borosilicate Glass Containing Savannah River Plant Waste

Description: Effects of internal alpha radiation on borosilicate glass, a perspective matrix for long-term storage of Savannah River Plant (SRP) radioactive waste, were evaluated in samples containing 45 wt % simulated waste (Fe(OH)/sub 3/--MnO/sub 2/) and either 0.5 wt % /sup 244/Cm or 1 wt % /sup 238/Pu. A glass containing /sup 238/Pu without waste was also studied for comparison. The glasses were examined for changes in physical stability, leachability, and dilatation. Alpha dose rates in the test glasse… more
Date: May 1, 1978
Creator: Bibler, N. E. & Kelley, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Complex fragments from excited actinide nuclei: A new test of the finite range model

Description: Complex fragments ranging in charge from 7less than or equal toZless than or equal to45 have been detected in binary coincidence following the reaction of 8.4 MeV/u/sup 232/Th+/sup 12/C, and are shown to arise from the binary decay of a /sup 244/Cm compound nucleus. This work confirms earlier radiochemical observations of very light fragments in the fission fragment mass distribution, establishes their binary character, and interprets their yield in terms of finite range potential energy barrie… more
Date: May 1, 1988
Creator: Sarantities, D. G.; Bowman, D. R.; Wozniak, G. J.; Charity, R. J.; Liu, Z. H.; McDonald, R. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The design of the DUPIC spent fuel bundle counter

Description: A neutron coincidence detector had been designed to measure the amount of curium in the fuel bundles and associated process samples used in the direct use of plutonium in Canadian deuterium-uranium (CANDU) fuel cycle. All of the sample categories are highly radioactive from the fission products contained in the pressurized water reactor (PWR) spent fuel feed stock. Substantial shielding is required to protect the He-3 detectors from the intense gamma rays. The Monte Carlo neutron and photon cal… more
Date: May 1, 1997
Creator: Menlove, H. O.; Rinard, P. M.; Kroncke, K. E. & Lee, Y. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Distribution of sup 137 Cs, sup 90 Sr, sup 238 Pu, sup 239 Pu, sup 241 Am and sup 244 Cm in Pond B, Savannah River Site

Description: The gradual senescence of present-day operating nuclear facilities, and resultant contamination of aquatic and terrestrial ecosystems, emphasize the importance of understanding the behavior of radionuclides in the environment. Observations and deductions concerning mechanisms of radionuclide transport can contribute significantly to knowledge of fundamental ecological processes. This study emphasized the ecosystem-level distribution of several long-lived radionuclides in an abandoned reactor co… more
Date: May 1, 1989
Creator: Whicker, F. W.; Pinder, J. E., III; Bowling, J. W.; Alberts, J. J. & Brisbin, I. L., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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