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ALPHA-GAMMA ANGULAR CORRELATION MEASUREMENTS WITH LIQUID SOURCES

Description: Alpha-gamma angular correlation measurements were made with solid sources of Am/sup 243/ and with liquid sources containing either Am/sup 243/ or an even-even alpha emitter in dilute perchloric acid solutions. Even-even alpha emitters studied are U/sup 232/, Th/sup 230/, and Ra/sup 226/ . Thicknesses of the soli d sources were controlled so that the neptunium recoils from one source were stopped in Am/sub 2/O/sub 3/, while recoils from the other sources were stopped in the aluminum, gold, or mica backing on which the sources were vaporized. The liquid sources were films consisting of 3 microliters of solution placed between a rubber hydrochloride membrane and a microscope cover glass, 1 cm/sup 2/ in circular cross section. The perchloric acid concentration of the liquid sources ranged from 0.5 to 3.0 molar. All of the angular correlations obtained with solid Am/sup 243/ sources were attenuated, the average attenuation coefficients being 0.29 450 deg C in a 0.01 for sources in which recoils were stopped in Am/sub 2/O/sub 3/, 0.20 450 deg C in a 0.01 for sources in which recoils were stopped in mica, 0.52 450 deg C in a 0.02 for sources in which recoils were stopped in gold, and 0.67 450 deg C in a 0.01 for sources in which recoils were stopped in aluminum. Unattenuated angular correlations were obtained with liquid sources containing Am/sup 243/ in 0.5 M and 1.0 M HClO/sub 4/ . For liquid sources containing Am/sup 243/ in 3.0 M HClO/sub 4/, the correlation was attenuated, with an average attenuation coefficient of 0.86 450 deg C in a 0.01. Attenuated angular correlations were also found with liquid sources containing an even-even nuclide in dilute aqueous solutions The average attenuation coefficients for the even-even nuclide liquid sources were G/sub 2/ = 0.75 450 deg C in a 0.05 ...
Date: February 1, 1963
Creator: Murphy, E.S. Jr.
Partner: UNT Libraries Government Documents Department

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Classification of decommissioning wastes. Addendum 2

Description: The radioactive wastes expected to result from decommissioning of the reference boiling water reactor power station are reviewed and classified in accordance with 10 CFR 61. The 18,949 cubic meters of waste from DECON are classified as follows: Class A, 97.5%; Class B, 2.0%; Class C, 0.3%. About 0.2% (47 cubic meters) of the waste would be generally unacceptable for disposal using near-surface disposal methods.
Date: September 1, 1984
Creator: Murphy, E.S.
Partner: UNT Libraries Government Documents Department

Analysis of freight train accident statistics for 1972-1974

Description: Both train speed and dollar damage have been used in transportation studies as measures of accident severity. Analysis of freight train accident data for the three year period, 1972-74 showed that, in general, as speed increases dollar damage to railroad property also increases. A greater percentage of high speed than low speed accidents result in high dollar damage. Factors, in addition to speed, that can have an important effect on accident severity include the type of accident, the kinds of railcars and other equipment involved, and the geographical environmental of the accident. Threshold levels of accident stresses (e.g., impact and puncture forces and fire temperature and duration) are required to compromise the integrity of shipping containers used for the transport of radioactive materials. Analyses of accident severity using either speed or dollar damage as a basis can provide some insights into the possible risks involved in transport of radioactive materials. however, care must be taken in the strict use of results since there is no direct correlation between either speed or dollar damage and cask failure threshold levels.
Date: May 1, 1978
Creator: Murphy, E.S.
Partner: UNT Libraries Government Documents Department

Technology, safety and costs of decommissioning a reference pressurized water reactor power station. Classification of decommissioning wastes. Addendum 3

Description: The radioactive wastes expected to result from decommissioning of the reference pressurized water reactor power station are reviewed and classified in accordance with 10 CFR 61. The 17,885 cubic meters of waste from DECON are classified as follows: Class A, 98.0%; Class B, 1.2%; Class C, 0.1%. About 0.7% (133 cubic meters) of the waste would be generally unacceptable for disposal using near-surface disposal methods.
Date: September 1, 1984
Creator: Murphy, E.S.
Partner: UNT Libraries Government Documents Department

Decommissioning of commercial shallow-land burial sites

Description: Estimated costs and safety considerations for decommissioning LLW burial grounds have been evaluated. Calculations are based on a generic burial ground assumed to be located at a western and an eastern site. Decommissioning modes include: (1) site stabilization followed by long-term care of the site; and (2) waste relocation. Site stabilization is estimated to cost from $0.4 million to $7.5 million, depending on the site and the stabilization option chosen. Long-term care is estimated to cost about $100,000 annually, with somewhat higher costs during early years because of increased site maintenance and environmental monitoring requirements. Long-term care is required until the site is released for unrestricted public use. Occupational and public safety impacts of site stabilization and long-term care are estimated to be small. Relocation of all the waste from a reference burial ground is estimated to cost more than $1.4 billion and to require more than 20 years for completion. Over 90% of the cost is associated with packaging, transportation, and offsite disposal of the exhumed waste. Waste relocation results in significant radiation exposure to decommissioning workers.
Date: January 1, 1979
Creator: Murphy, E.S. & Holter, G.M.
Partner: UNT Libraries Government Documents Department

Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Main Report

Description: Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 1 (Main Report) contains background information and study results in summary form.
Date: June 1, 1980
Creator: Murphy, E. S. & Holter, G. M.
Partner: UNT Libraries Government Documents Department

Criticality experiments with low enriched UO/sub 2/ fuel rods in water containing dissolved gadolinium

Description: The results obtained in a criticality experiments program performed for British Nuclear Fuels, Ltd. (BNFL) under contract with the United States Department of Energy (USDOE) are presented in this report along with a complete description of the experiments. The experiments involved low enriched UO/sub 2/ and PuO/sub 2/-UO/sub 2/ fuel rods in water containing dissolved gadolinium, and are in direct support of BNFL plans to use soluble compounds of the neutron poison gadolinium as a primary criticality safeguard in the reprocessing of low enriched nuclear fuels. The experiments were designed primarily to provide data for validating a calculation method being developed for BNFL design and safety assessments, and to obtain data for the use of gadolinium as a neutron poison in nuclear chemical plant operations - particularly fuel dissolution. The experiments program covers a wide range of neutron moderation (near optimum to very under-moderated) and a wide range of gadolinium concentration (zero to about 2.5 g Gd/l). The measurements provide critical and subcritical k/sub eff/ data (1 greater than or equal to k/sub eff/ greater than or equal to 0.87) on fuel-water assemblies of UO/sub 2/ rods at two enrichments (2.35 wt % and 4.31 wt % /sup 235/U) and on mixed fuel-water assemblies of UO/sub 2/ and PuO/sub 2/-UO/sub 2/ rods containing 4.31 wt % /sup 235/U and 2 wt % PuO/sub 2/ in natural UO/sub 2/ respectively. Critical size of the lattices was determined with water containing no gadolinium and with water containing dissolved gadolinium nitrate. Pulsed neutron source measurements were performed to determine subcritical k/sub eff/ values as additional amounts of gadolinium were successively dissolved in the water of each critical assembly. Fission rate measurements in /sup 235/U using solid state track recorders were made in each of the three unpoisoned critical assemblies, and in the near-optimum ...
Date: February 1, 1984
Creator: Bierman, S.R.; Murphy, E.S.; Clayton, E.D. & Keay, R.T.
Partner: UNT Libraries Government Documents Department

A SAFETY AND ECONOMIC STUDY OF SPECIAL TRAINS FOR SHIPMENT OF SPENT FUEL

Description: This report presents the results of a study to compare and evaluate the safety and economics of spent fuel shipments by special trains relative to shipments by conventional freight trains. The safety of special trains was investigated by analyzing data from the Federal Railroad Administration for freight train accidents occurring during the period 1972-1974. The economic analysis compared the cost of spent fuel shipments by special trains and by conventional freight trains.
Date: December 1, 1977
Creator: Loscutoff, W. V.; Murphy, E. S.; Clark, L. L.; McKee, R. W. & Hall, R. J.
Partner: UNT Libraries Government Documents Department