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Waste Treatment and Disposal Progress Report for June and July 1961

Description: 7 7 6 4 : 9 8 9 6 5 : 9 aluminum nitrate waste was calcined in the close-coupled continuous evaporator-pot calciner unit. Waste oxides from TBP-25 waste were incorporated into glassy materials after the addition of phosphate and borate fluxing agents. Melts formed at 850 to 950 deg C were glassy solids when cooled and had densities from 2.41 to 2.47 g/ml. Waste volurne reduction factors were from 7.6 to 9.3. Low-Level Waste Treatment. A demonstration run was completed in the 60 liters/hr scaven… more
Date: October 24, 1961
Creator: Blanco, R. E. & Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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1A HEAT EXCHANGER LEAK TEST. CORE I, SEED 2. Test Evaluation. Section 2

Description: An investigation was conducted to determine which tubes of the 1A loop heat exchanger are leaking. Air pressure and probing tests are inconclusive and cannot be used to verify chemical sampling. (J.R.D.)
Date: July 24, 1961
Partner: UNT Libraries Government Documents Department
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Production test IP-402-A, Irradiation of Zr-2 cladding studies capsules

Description: The objective of this production test was to evaluate the effects of Zr-2 jacket uniformity, thickness, and temperature on non-uniform clad straining. Test details are provided.
Date: March 24, 1961
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Hazards review Phase 1 fission product processing in B-plant

Description: Future operation of B-Plant for Phase I fission product processing involves may of the hazards associated with current chemical Processing Department activities in both the Purex and Redox Plants. The specific B-Plant hazards under Phase I operations are discussed in this report from the standpoint of comparable Purex and Redox hazards.
Date: August 24, 1961
Creator: Michels, L. R. & Zahn, L. L.
Partner: UNT Libraries Government Documents Department
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105-C overboring thirteen tube outage, March 6, 1961--March 10, 1961

Description: C Reactor was shut down on a scheduled basis at 8:30 a.m. March 6, 1961 for the purpose of overboring 17 process channels. this report will cover that outage and discuss problems encountered in completing the tasks involved in overboring.
Date: March 24, 1961
Creator: Munro, C. A.
Partner: UNT Libraries Government Documents Department
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Fuel Shipping Container Test. Core I, Seed 1. Section 1. Test Results T-643717-A

Description: A test was performed at the Shippingport PWR, whose purpose was to determine the amount of heat the fuel shipping container cooling system was capable of removing while in a state of equilibrium. Studies were also conducted to determine if after four hours of operation, the increase of the internal wall temperature was less than 30 deg F, and finally, to determine the effects of loss of cooling water from the fuel shipping container. (auth)
Date: April 24, 1961
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor Final Safeguards Report, Volume 6: Environmental Analysis OF NS "Savannah" Operation at Camden

Description: "An analysis is presented of the accidental release of activity following the operation of the NS "Savannah" at the New York Shipbuilding Corporation docks in Camden, New Jersey. Although a number of accidents are considered, the report is primarily concerned with the environmental activity levels and subsequent exposures which would result from the "maximum credible accident" (p. v).
Date: January 24, 1961
Creator: Cottrell, W. B.; Parker, F. L.; Mann, L. A. & Schmidt, G. D.
Partner: UNT Libraries Government Documents Department
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THORIUM BREEDER REACTOR EVALUATION. PART 1. FUEL YIELD AND FUEL CYCLE COSTS IN FIVE THERMAL BREEDERS

Description: The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GGBR), and deuterium- moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site. The maximum annual fuel yields were 1.5 mills/ kwhr. The minimum estimated fuel cycle costs were … more
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Partner: UNT Libraries Government Documents Department
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THORIUM BREEDER REACTOR EVALUATION. PART I. FUEL YIELD AND FUEL CYCLE COSTS IN FIVE THERMAL BREEDERS. APPENDICES

Description: The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GCBR), and deuterium- moderated gascooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected with continuous processing of fuel and fertile streams. The maximum annual fuel yields were 16, 7, 4, 4, and 4.5%/yr, respectively at a fuel cycle cost of 1.5 mills/kwhr… more
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Partner: UNT Libraries Government Documents Department
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DIRECT REDUCTION OF URANIUM HEXAFLUORIDE TO URANIUM METAL BY SODIUM (DRUHM PROCESS)

Description: The chemical feasibility of the direct, continuous reduction of UF/sub 6/ to U with Na was shown in several tests. Up to 93.5% of the U content of UF/sub 6/ continuously reduced by Na in a reaction vessel was recovered as massive U metal of acceptable purity. A semicontinuous reactor for continuous reduction is described. (D.L.C.)
Date: May 24, 1961
Creator: Scott, C.D.
Partner: UNT Libraries Government Documents Department
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POLFIT II, AN IBM 7090 PROGRAM FOR POLYNOMIAL LEAST SQUARES FITTING

Description: A program was written to perform polynomial least squares fits on the IBM 7090 computer. Weighting factors may be included with the data if desired. The program includes a subroutine which does the fit and furnishes the calling program with the coefficients, standard errors in the coefficients, staandard error of fit, and information necessary to compute a complete error analysis; and a calling program which reads input, calls the subroutine, and writes requested output. The subroutine may be u… more
Date: April 24, 1961
Creator: Lietzke, M.P.
Partner: UNT Libraries Government Documents Department
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EGCR Graphite Permeability Tests: Results of Forced Flow Experiments on Egcr Moderator-Grade Graphite

Description: Helium-permeability and porosity were determired at room temperature for specimens from a typical EGCR moderator-grade graphite block. Permeability, at a mean pressure of 2 atm, ranged from 26 to 200 (av. 86.5) millidarcys. Permeability data indicated that turbalent flow was never obtained with helium in these tests and that helium permeating the moderator graphite at EGCR operating conditions (taken to be: 600 deg C; DELTA P, 10 lb/in./sup 2/ per inch of graphite; mean P, 400 lb/in./sup 2/) wa… more
Date: March 24, 1961
Creator: Ward, W. T. & Truitt, J.
Partner: UNT Libraries Government Documents Department
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RADIATION SURVEY OF BEWI AND ASEWI REFUELING. CORE 1, SEED 1. Test Results T-643709

Description: The radiation survey of the Blanket Exit Water Instrumentation assemblies Core I, Seed 1 was performed on January 15 and 16, 1960, approximately 100 days after reactor shutdown at 5806 EFPH. The observed radiation levels varied with height from 150 to 500 mr/hr; the highest activity was found at the bottom of both support tubes of each of the four assemblies monitored, which, in operation, would be located 5 in. above the top of the blanket fuel assembly. The two inner port Blanket Exit Water I… more
Date: April 24, 1961
Partner: UNT Libraries Government Documents Department
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1B HEAT EXCHANGER LEAK TEST. CORE I, SEED 1. Test Results

Description: Descriptions are given of various procedures used in determining leaks in the tubes of the 1B heat exchanger. Air pressurization tests determined leakage and leak rate of nine tubes. The leak-location-detector-probe method was found promising for locating defects along the length of the tube. Results of the probalog, dye-penetrant, and ultrasonic tests proved inconclusive in determining leak locations. (B.O.G.)
Date: February 24, 1961
Partner: UNT Libraries Government Documents Department
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REACTOR PHYSICS STUDIES FOR THE FINAL CONCEPTUAL DESIGN OF THE ADVANCED TEST REACTOR

Description: A detailed account of the reactor physics studies for the final conceptual design of the Advanced Test Reactor is presented. The diffusion theory methods used for calculations of flux distributions and reactivity effects are described and compared with measurements and with higher order approximations to transport theory. These comparisons show diffusion theory to be adequate for the ATR conceptual design. Two-dimensional flux distributions for a number of shim control conditions and experiment… more
Date: March 24, 1961
Creator: Marsden, R.S. ed.
Partner: UNT Libraries Government Documents Department
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FINAL CYCLE PLUTONIUM RECOVERY BY AMINE EXTRACTION

Description: The flowsheet visualized from development work thus far for final plutonium recovery and purification will accept as feed a Purex partition stream without feed adjustment beyond the usual reoxidation. Extraction with trilaurylamine at approximately 0.3M appears suitable for 20 to 60 g Pu/liter product from 0.5 to 2 g Pu/liter feed. Scrubbing with either ((2 M or))2 M HNO/ sub 3/ is possible. Acetic acid is at present the first choice for stripping agent, with oil-soluble and aqueous-soluble org… more
Date: May 24, 1961
Creator: Coleman, C.F.
Partner: UNT Libraries Government Documents Department
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Atomic Energy Levels in Crystals

Description: Report discussing discrete energy levels observed within certain crystals which are due to perturbations of energy levels of the free ion by an electrostatic field arising from the crystal lattice. The analytic procedures for determining the field from the charge configuration are given, and the resulting fields are classified according to their symmetry. After a general survey of group-theoretical ideas, the applicable groups are analyzed in detail, and characters appropriate for both integral… more
Date: February 24, 1961
Creator: Prather, John L.
Partner: UNT Libraries Government Documents Department
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A Recoil Study Of The Reaction C12(p,pn)C11 [formula]

Description: Recoil ranges of C11 from the reaction C12(p,pn)C11 are presented for incident proton energies from 0.25 to 6.2 Gev. From these data it is concluded that a neutron evaporation mechanism cannot be the major mechanism. The result for incident energies of 3 and 6.2 Gev are consistent with a fast reaction consisting of a single inelastic nucleon-nucleon collision. Assuming this mechanism, an average kinetic energy of 19 Mev can be deduced for the struck neutron (before the collision) in the C12 nuc… more
Date: October 24, 1961
Creator: Singh, Sarjant & Alexander, John M.
Partner: UNT Libraries Government Documents Department
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Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders

Description: The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas cooled graphite-moderated (GGBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Partner: UNT Libraries Government Documents Department
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