92 Matching Results

Search Results

Advanced search parameters have been applied.

A Summary Review of Mound Laboratory's Experience in D & D of Radioactive Facilities 1949-1973

Description: The objective of Mound Laboratory's Decontamination and Decommissioning (D&D) projects has been the effective termination of radioactive material processing facilities with no significant personnel exposures or environmental releases. This objective must be met with available resources and manpower. Mound has effectively decontaminated and/or decommissioned four major facilities in the 1949 through 1973 time period. Many minor areas were also decontaminated and/or decommissioned during this period. The major D & D projects involved the following isotopes: polonium-210, radium-226, actinium-227, and plutonium-238. To achieve a D & D status, Mound has employed several control and decontamination techniques such as: "Navy Cocooning", entombment, removal, foaming, bagging, tents, chutes, portable exhausters, dry ice, vents, bubble suits, three-zones, fire watches, painting and sealing, in-line cleaning, high pressure water blaster, and chemical cleaning.
Date: June 1, 1974
Creator: Garner, J. M. & Davis, W. P.
Partner: UNT Libraries Government Documents Department

Thermal shock analysis of ceramic multihundred watt spheres

Description: The thermal fracture resistance of plutonia Multihundred Watt (MHW) fuel spheres was analyzed assuming boundary conditions of (1) constant heating or cooling rate for the sphere surface, (2) heating or cooling with a constant surface heat transfer coefficient at the sphere surface, and (3) heating or cooling the sphere surface solely by radiation. Thermal damage resistance (mechanical weakening) of MHW spheres was analyzed in terms of the fracture energy and crack system present in the fuel. Using available property data for porous PuO/sub 2/ between 400 and 1200 deg C, and estimating other properties from available data for UO/sub 2/ and ThO/sub 2/ the thermal shock conditions that cause fracture of the fuel sphere were estimated. Experimental values for the tensile fracture strength and the elastic modulus of the fuel as functions of temperature are presently not available and estimates were made of these properties. (auth)
Date: March 25, 1974
Creator: Tennery, V.J.
Partner: UNT Libraries Government Documents Department

Stability of complexed Rover dissolver solutions containing high concentrations of niobium, fluoride-ion, and aluminum

Description: The processing of nuclear rocket (Rover) fuels requires high concentrations of hydrofluoric acid and nitric acid in the dissolver solution to dissolve the uranium and niobium. The resulting dissolver solutlon is highly corrosive and requires the addition of aluminum nitrate to complex the free fluoride'' and reduce corrosion on stainless steel processing equipment located downstream from the dissolver. The dissolver solution is very sensitive to aluminum nitrate addition; excessive aluminum nitrate results in precipitation of Nb/sub 2/O/sub 5/. Insufficient aluminum nitrate results in precipitation of AlF/ sub 3/, and the solution remains corrosive. The stability range of the complexed dissolver solution is narrow and time dependent. The stability range was determined expenimentally to vary from 24--30% for a 2-hr period and from 0-10% for a 24-hr period. The stability range is increased to 40% over a 5-day peniod when the solution is diluted and adjusted for solvent exrraction feed. (auth)
Date: February 1, 1974
Creator: Rindfleisch, J.A.
Partner: UNT Libraries Government Documents Department

Experimentally determined neutron and gamma-ray spectra from an encapsulated Cm$sub 2$O$sub 3$ power source

Description: The experimentally determined neutron and gamma ray spectra of a Cm/sub 2/O/sub 3/ spontaneously fissioning source are presented. The neutron spectrum is given for the energy range 30 keV to 10 MeV, while the gamma ray spectrum spans the energy range 205 keV to 12 MeV. (auth)
Date: March 1, 1974
Creator: Freestone, R.M. Jr.
Partner: UNT Libraries Government Documents Department

Guide to the acceptance criteria for radioisotopic heat sources

Description: During the development phases of heat source programs (the fabrication for design verification, engineering evaluation, etc.), heat sources and test capsules are often required prior to the formalization of specifications and drawings. Furthermore, there are also programs where the quantities and technology are such that a detailed and unique set of documentation is not justified. Consequently, this document is intended to be a general guide to the criteria applicable in evaluating the acceptability of radioisotopic heat sources and test capsules when they are produced under these circunnstances. The guidelines are general in nature, since many applications of heat sources have unique requirements, but typical values are given where practicable. This document is written in the format of a general specification to enhance its usefulness. (auth)
Date: February 20, 1974
Creator: Coffey, D.L.
Partner: UNT Libraries Government Documents Department

Test of fusible insulation for a proposed isotope power unit

Description: In support of the Isotope Kilowatt Program, an evaluation test of the full-scale simulated thermoelectric power generation system was made. The test was run with 6.5 in. of fusible insulation around the heat block-shield to determine the system heat losses. A loss of 10% of full power was obtained with the system operation at a heat block-shield surface temperature of 1100 deg F and an argon pressure of 1.0 psig. A test was run to determine the thermal coupling between the heat block-shield and 12 heat pipes with 12 simulated thermoelectric generators. A heat pipe condenser temperature of 1040 deg F was obtained at a heat block-shield surface temperature of 1150 deg F at a total power input of 34 kW. A loss-of-coolant accident test was made to determine the maximum fuel capsule surface temperature reached during a meltdown of the fusible insulation. The meltdown results yielded a maximum fuel capsule surface temperature of 2175 deg F and an equilibrium temperature of 2070 deg F. (auth)
Date: April 1, 1974
Creator: Lackey, M.E.
Partner: UNT Libraries Government Documents Department