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AECOP Task Assignment No. 5

Description: This document details information provided in support of AECOP Task Assignment No. 5, ``Conversion of Np-237 to Pu-238.`` Conversion efficiency of each production reactor for a range of product purities and for the anticipated range of available flux levels is given.
Date: July 27, 1967
Creator: Woods, W.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report

Description: An analytical trajectory and aerothermodynamic analysis of a satellite containing a Task 2 thermoelectric generator was completed. A 300-statute mile circular polar orbit was used for this analysis and the launch was assumed to be from Vandenberg Air Force Base. Results of this study show that upon natural decay from a successful mission, the radio-cerium fuel will burn up in space at high altitude, thus only a very minor amount of radio cerium will be released to the stratosphere. A complete a… more
Date: December 27, 1960
Creator: Oehrli, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Angular Distribution of Fission Fragments From the Fast Neutron-Induced Fission of U-234

Description: Submitted to Univ. of Tennessee, Knoxville. The fast neutron-induced fission cross section of U/sup 234/ was measured from threshold to 4-Mev neutron energy. A maximum of 1.26 barns was found at 850 kev followed by a minimum of 1.10 barns at 8050 kev. The angular ani-sotropy of the fragment distribution was measured for neutron energies from 400 kev to 4 Mev. Extrema in the ratio sigma /sub f//( sigma /sub f(90 deg ) were found at 500, 850, and 1050 kev; the distribution at 500 kev showing a ma… more
Date: August 27, 1962
Creator: Lamphere, R. W.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
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Applied Health Physics Annual Report for 1960

Description: Although there were the ususl fluctuations in background at certain of the monitoring stations, the contamination levels recorded do not differ significantly from those of the previous year except that there appears to be a slight trend downward. Data are tabulated. This downward trend can be attributed to a curtailment of operations at the Laboratory, the gradual implementation of the containment program, and a curtailment in world-wide weapons testing. Tall-out data are included. Two personne… more
Date: July 27, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aqueous Processing of Thorium Fuels. Part 2

Description: The status of aqueous processing methods for Th fuels is reviewed. A specially designed 320 ton shear was successfully tested for chopping full size simulated Consolidated Edison type unirradiated assemblies into 0.25-1.5 in. lengths. Pieces about 0.5-in. long are preferred since the core pellets are more severely crushed during the chopping operation, and consequently, the rate of core dissolution is enhanced. The Darex (dtlute aqua regia) and Sulfex (4 to 6 M sulfuric acid) processes for diss… more
Date: November 27, 1962
Creator: Blanco, R. E.; Ferris, L. M.; Watson, C. D. & Rainey, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Artificial Heart Pump (Additional Endogenous Heat) Program

Description: Three plutonium-238 radioisotope-powered heat sources were developed and fabricated at Mound Laboratory for use by Thermo Electron Engineering Corporation (TEECO) in the Artificial Heart Pump (Additional Endogenous Heat) Program. These sources contained doubly encapsulated plutonum-238 metal; two had a thermal power of 15(+2-0) W and one had 25(+0-2) W. Details of the design, fabrication, and testing of the heat sources are given in this report. Two of the heat sources (one 15-W and one 25-W) w… more
Date: January 27, 1969
Creator: Davis, N. E.; Davenport, C. H. & Kelly, D. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Basis for design scope: Plutonium Reclamation Facility, Z Plant, Project CAC-880

Description: This report discuss the design of the Plutonium Reclamation Facility the capacity of which will be 300 kilograms per month or 3600 kilograms per year or plutonium. The subject facility, as the name implies, must be extremely flexible in its ability to handle a wide variety of feed materials. The new facility will be operating on a three-shift day, five-day week, 40-week year with an overall efficiency of 75 percent; twelve weeks per year will be required for ``turnaround`` time to enable campai… more
Date: April 27, 1960
Creator: Braden, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Behavior of Fission Products Released Into a Steam-Air Atmosphere From Overheated UO {Sub 2} Previously Irradiated to 20,000 MWD/T (Nuclear Safety Pilot Plant Run No. 14, Part I)

Description: This report summarizes the results of the first run made in the Nuclear Safety Pilot Plant using Zircaloy-2 clad UO2 irradiated to 20,000 MWD/T and reirradiated shortly before the run to replenish the inventory of short-lived fission products.
Date: September 27, 1967
Creator: Parsly, L. F. & Row, T. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CALCULATIONS OF THERMAL-NEUTRON FLUX DISTRIBUTIONS IN CONCRETE-WALLED DUCTS USING AN ALBEDO MODEL WITH MONTE CARLO TECHNIQUES

Description: BS>When radiation shields are penetrated by ducts, the gamma rays resulting from the radiative capture of lowenergy neutrons in the duct walls can be principal contributors to the total dose along the duct. In order to calculate the effect of these capture gamma rays, the distribution of low-energy neutrons in the ducts must be known. This report presents calculations of low- energy neutron distributions in concrete-walled ducts by a method in which an albedo model and a Monte Carlo technique w… more
Date: January 27, 1964
Creator: Cain, V.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization of commercial aluminate, silicate, and Zero-X materials

Description: Lithium aluminate and lithium silicate powders (Lithium Corporation of America) and Zero-X pellets (Ferro Corporation) have been analyzed spectrochemically, by x-ray diffraction, and for lithium, carbon, and water content. These data are presented along with some important physical constants of the materials. Aluminate and silicate powders are incompletely calcined, containing up to 3 wt percent residual lithium carbonate. They have lithium contents that are sub-stoichiometric by as much as 20 … more
Date: January 27, 1966
Creator: Gurwell, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical decontamination of Hanford production reactors

Description: The conduct of outage work in the discharge areas of the Hanford production reactors has always been complicated by personnel exposure to radiation from the contaminants which accumulate in the effluent water piping in the course of normal operations. These containments represent trace impurities in the cooling water, together with corrosion products, which are irradiated in passing through the reactor and then deposit in the unshielded rear face piping. Radioactive residues also accumulate on … more
Date: June 27, 1963
Creator: Hauff, T. W.; Jensen, H. F. & Smith, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, July 1960

Description: A critical review of the literature revealed no experiments on uranyl ion transfer from an aqueous to a tributyl phosphate phase which positively measured the kinetics of the chemical reaction at the interphase. Drawing isorhythmic lines on a three component diagram gives a complex correlation for the compaction of three sizes of glass beads. Neither the use of thoria sols nor high feed solution concentrations of thorium nitrate gave any significant increase in mean particle diameters over thos… more
Date: October 27, 1960
Creator: Whatley, M E; Haas, P A; Horton, R W; Ryon, A D; Suddath, J C & Watson, C D
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparative reactor flux spectra

Description: This document is explanatory in nature and is intended to clarify certain questions about reactor neutron flux spectra in various AEC production facilities. Simplified models are used to illustrate neutron ``temperature,`` spectral ``hardening,`` and the so-called ``Westcott R.``
Date: November 27, 1963
Creator: Gumprecht, R. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion Mechanism of Zirconium and Its Alloys--Diffusion of Oxygen in Zirconium Dioxide

Description: The diffusion rate of O in anion-deficient zirconia, ZrO/sub 1.994/, was determined by the interface migration of stoichiometric oxide and is represented by the equation D = 0.055 exp (--33,400 surface proces 3100/RT). A comparison was made with other processes that occur in the metal and the oxide. Excellent agreement was noted between activation energies of O diffusion in ZrO/sub 1.944/ and those for parabolic or cubic oxidation in both air and water. It appears that O diffusion in the oxide … more
Date: July 27, 1962
Creator: Douglass, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination Studies: Battelle-Northwest Laboratories, December 1964-- August 1965

Description: From ninth meeting of the USAEC reactor decontamination information exchange group; Washington, District of Columbia, USA (1 Sep 1965). The decontamination activity described includes: laboratory studies to evaluate reagents, and actual decontamination of 2 steam generators at New Production Reactor. ln laboratory tests, a proprietery oxalic acid solution appeared to be more effective th:dn sny other tried. No excessive corrosion was noted. Special reegents to dissolve high fired ceramic core m… more
Date: July 27, 1965
Creator: Ayres, J. A.; Larrick, A. P.; Perrigo, L. D. & Weed, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Densities of Ammonium Fluoride-Ammonium Nitrate-Ammonium Hexafluozirconate Solutions

Description: The densities of various Zirflex-type solutions at 25 gas-cooled C can be expressed by the equation: p calc = (0.99710 + 0.03l57 m) + (0.02046 - 0.002659 m)c -(0.0033460.000703 m)c3/2 + 0.14349x + 0.49z where m = moles liter/ sup -1/ NH/sub 4/NO/sub 3/, c = moles liter/sup -1/ NH/sub 4/F, x = moles liter/ sup -1/ (NH/sub 4/)/sub 2/ZrF/sub 6/, and z = moles liter/sup -1/ UO/sub 2/(NO/ sub 3/)/sub 2/. This eq uation fits the data with a sigma value of 0.00018 g/ml for NH/sub 4/FNH/sub 4/NO/sub 3/… more
Date: October 27, 1960
Creator: Teague, J. L. & Pearson, D. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dependence of the yield of the ({alpha},n) reaction on alpha particle energy

Description: Neutron yields for alpha particle reactions with beryllium, boron, carbon, magnesium, and oxygen are calculated. The dependence on energy of the incoming alpha particles is analyzed for yield. Calculations are varied for different sets of cross section data.
Date: March 27, 1967
Creator: Tsenter, E. M. & Silin, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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