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Hazards Report for Step Transient Loading Tests on the SM-1 : Task XII

Description: Abstract: This technical report evaluates hazards involved with SM- 1 plant response and system performance tests (Task XII), to determine the response of the SM-1 plant to step electrical and steam load changes. The report describes the changes in plant equipment and operating procedures for this task and evaluates these changes for possible additional hazards to those described in APAE No. 2, Revision 1, "Hazards Summary Report for the Army Package Power Reactor SM-1."
Date: February 1, 1962
Creator: Pomeroy, D. L.
Partner: UNT Libraries Government Documents Department
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Production test IP-466-A test of the 190 turbine pumps at KE(KW) Rector (Project CGI-844)

Description: The purpose of this test is to provide for adequate testing of the new steam turbine pumps. This will cover the tests required for the acceptance of these new items as per ATP-2588 and for any additional testing required to ensure reactor emergency cooling adequacy and reliability. A further objective is to provide the safety requiring by which the objectives of the ATP-2588 may be accomplished. A steam pump is being installed in each of the 190-K buildings to provide an additional secondary su… more
Date: February 1, 1962
Creator: Jones, S. S.
Partner: UNT Libraries Government Documents Department
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Cesium-137 index for nuclear materials content of coating waste

Description: Cs-137 has been chosen as a possible index of the plutonium and uranium in coating waste. This index is a stable ratio as long as the plutonium formation rate (Pu/MD) is stable. Calculations are presented for Purex and Redox. It is recommended that the Cs-137 index method be used for determining nuclear materials content in coating waste at both Purex and Redox; this will result in higher but more accurate statements of Pu, U losses in coating waste.
Date: February 1, 1962
Creator: Schneider, R. A. & Zimmer, W. H.
Partner: UNT Libraries Government Documents Department
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Significance of Urine Uranium Excretion Data

Description: No Description Available.
Date: February 1, 1962
Creator: Lippmann, M.; Ong, Long D. Y. & Harris, William B.
Partner: UNT Libraries Government Documents Department
open access

Progress Report on Neutron Radiography

Description: BS> The potential advantages of neutron radiography as an inspection method are discussed along with a historical review and discussions of neutron sources and detectors. The results of the current investigation of neutron-image detectors are discussed in regard to photographic speed, relative neutron-gamma response, and resolution comparisons. Two neutron-image detecting methods are discussed. In one, the direct-exposure method, both the converter screens and the film are exposed to the neutro… more
Date: February 1, 1962
Creator: Berger, H. & McGonnagle, W.J.
Partner: UNT Libraries Government Documents Department
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TRANSPORT OF NOBLE GASES IN GRAPHITES. Progress Report for the Period January 31, 1961 to January 31, 1962

Description: A model was derived for the diffusion of gases in porous media in the absence of temperature and pressure gradients, in which portions of the medium are visualized as a collection of uniformly distributed dust'' particles (giant molecules) which are constrained to be stationary. Thus, it was possible to derive all the desired results from rigorous diffusion equations for multi- component mixtures. The results apply over the entire pressure range from the Knudsen region to the normal diffusion r… more
Date: February 1, 1962
Creator: Truitt, J.; Smith, N. V.; Watson, G. M.; Evans, R. B., Ill, & Mason, E. A.
Partner: UNT Libraries Government Documents Department
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COMPONENT FEASIBILITY TEST REPORT FOR THE AMF ON-POWER REFUELING SYSTEM FOR THE DOUGLAS POINT PLANT

Description: Activities in a phase of CANDU I refueling machine development are reported which are concerned with obtaining test data for various system subcomponent parts. The basis for selecting those units requiring test was established through engineering evaluation of available information. Results of tests based on these requirements are included in the form of test reports. (J.R.D.)
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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Determination of Radiation Contamination Levels During Core I, Seed 2-Seed 3 Refueling Operations. Test Evaluation (T-643128)

Description: A record is presented of radiation contamination levels observed in the work area during the Core I Seed 2-Seed 3 refueling operations. The radiation levels for Seed 2-3 refueling were somewhat higher thand those for Seed 1-2 refueling in certain areas and are ascribed to operations being carried out under dry conditions. Maximum contamination levels were also higher, but the general contamination level was lower. The activity of canal water was higher and characterization was made on some of t… more
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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Carbide Fuel Development. Progress Report, September 15, 1961 to December 31, 1961

Description: Single phase, solid solution, UC-PuC powder was synthesized reproducibly from a mixture of the oxides and carbon. A simple method of monitoring the reaction was developed. UC-PuC-0.1 wt% Ni pellets of 93% theoretical density were made reproducibly, with some samples as high as 95% of theoretical denstty. The pellets contain minor amounts of (U,Pu)/sub 2/C/sub 3/ most of the time. Efforts to make reproducible 95%, single-phase material are under way. Microprobe analysis of UC-0.1 wt% Ni specimen… more
Date: February 1, 1962
Creator: Strasser, A. & Taylor, K.
Partner: UNT Libraries Government Documents Department
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THE DISTORTED-WAVE THEORY OF DIRECT NUCLEAR REACTIONS. I. "ZERO-RANGE" FORMALISM WITHOUT SPIN-ORBIT COUPLING, AND THE CODE SALLY

Description: The distorted-wave theory of direct nuclear reactions is presented in a unified manner, in which the effects of assuming various reaction mechanisms and nuclear models appear only in certain radial form factors. The zero-range approximation is used, and spin-orbit coupling is neglected in the distorted waves. Formulas are given for transition amplitudes, cross sections, and polarizations. A description is given of the IBM-704 computer code SALLY that is based on these formulas. (auth)
Date: February 1, 1962
Creator: Bassel, R.H.; Drisko, R.M. & Satchler, G.R.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Monthly Progress Letter for Month of January 1962

Description: Development work leading to comparison of co-precipitated and mechanically blended UO/sub 2/-- PuO/sub 2? powders is reported in which special emphasis was placed on blending trials, pellet sintering studies, and subsequent evaluation of pellets made with blended material. Homogeneity studies indicate that currently used procedures are unsatisfactory because particle buildup occurs during blending. Powder preparation via the oxalate route was continued along with PuO/sub 2/ moisture pickup stud… more
Date: February 1, 1962
Creator: Puechl, K.H.
Partner: UNT Libraries Government Documents Department
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The Chemistry of Niobium in Processing of Nuclear Fuels

Description: The chemical and industrial literature and laboratory work concerned with processing of niobium-containing nuclear fuels are reviewed. 57 references. (auth)
Date: February 1, 1962
Creator: Gens, T. A.
Partner: UNT Libraries Government Documents Department
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GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1961

Description: Progress is reported on investigations in support of the Experimental Gas-Cooled Reactor, the Pebble-Bed Reactor Experiment, Advanced reactor design and development, test facilities, components, and materials. Topics covered include EGCR physics, EGCR performance analyses, structural investigations, EGCR component and materials development and testing, EGCR experimental facilities, PBRE physics and design studies, fueled-graphite investigations, clad fuel development, design studies of advanced… more
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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The Uranium-Rich End of the Uranium-Zirconium System. Final Report- Metallurgy Program 3.1.3.

Description: The uranium-rich end of the uranium-zirconium alloy system was reinvestigated. The solubilities of zirconium in alpha and beta uranium were found to be 0.21 wt% at 662 deg C and 0.41 wt% at 693 deg C, respectively. The monotectoid decomposition of gamma /sub 1/ at 693 deg C and the eutectoid decomposition of t 662 deg C were confirmed. For alloys containing less than 150 ppm of oxygen by weight, the gamma /sub 1/ plus gamma /sub 2/ phase region boundaries were located at 4.5 and 22.0 wt% zircon… more
Date: February 1, 1962
Creator: Zegler, S. T.
Partner: UNT Libraries Government Documents Department
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Examination of Uranium-2 w/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I. Final Report-Program 6.1.11

Description: Six groups of U-2 wt% Zr fuel slugs were irradiated in the first core of the EBR-I to burnups of 0.080 to 0.189 at.% at calculated temperatures of 307 to 353 deg C. Two groups of cast specimens were found to be more dimensionally stable than four groups of wrought slugs. Of the wrought slungs, the as quenched group showed less tendency to grow than the three groups which had some annealing after quenching. Specimens at burnups of about 0.189 at.% and at 383 deg C showed the onset of swelling as… more
Date: February 1, 1962
Creator: Murphy, W. F.; Klank, A. C. & Paine, S. H.
Partner: UNT Libraries Government Documents Department
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PROCESSING OF POWER REACTOR FUELS SIXTEENTH QUARTERLY PROGRESS REPORT, JULY 1 TO OCTOBER 1, 1961

Description: In the semiworks dissolver, average currents were about 2000 amp during dissolution of stainless steel and about 1200 amp during dissolution of Zircaloy. These currents were obtained when the current was transferred to a fuel assembly by direct contact with the columbium basket. High dissolution rates are anticipated when the dissolver is modified so that the electrolyte makes the only electrical contact with the charge. Laboratory experiments were made to determine the important characteristic… more
Date: February 1, 1962
Creator: Rust, F.G. comp.
Partner: UNT Libraries Government Documents Department
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RADIOACTIVE FALLOUT FROM NUCLEAR WEAPONS TESTS. Proceedings of a Conference Held in Germantown, Maryland, November 15-17, 1961

Description: Thirty papers are presented reviewing AEC research projects related to fall-out from weapons tests. Reviews of specific related programs by representatives from Canada and the UK are also included. The scope of the conference includes characteristics of fall-out, atmospheric factors affecting deposition, distribution in the environment, and distribution in the food chain and man. Separate abstracts have been prepared for each paper. (C.H.)
Date: February 1, 1962
Creator: Klement, A.W. Jr. ed.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, February 1962

Description: Progress is reported on EBWR, BORAX-V, and development of liquid metal cooled reactors including EBR-I and -II. Developments in general reactor technology are reported in sections on physics, fuels, components, materials, engineering, and chemical separations. Other research and development is reported in advanced systems and nuclear ssfety. (J.R.D.)
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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The Photon Energy Response of Several Ionization Chamber Instruments

Description: The photon energy response of several radiation survey meters and pocket dosimeters was measured over an energy range of 8 to 1250 kev. Measurements were also taken with the meters in different orientations and with open and closed shield. The devices selected for these measurements are all ionization chamber instruments in routine or special use at the Los Alamos Scientific Laboratory. (auth)
Date: February 1, 1962
Creator: McKown, D. A. & Storm, E.
Partner: UNT Libraries Government Documents Department
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Strontium-90 Fueled Thermoelectric Generator Power Source for Five-Watt U.S. Coast Guard Light Buoy. Final Report

Description: The objectives of the SNAP 7A program were to design, manufacture, test, and deliver a five-watt electric generation system for a U. S. Coast Guard 8 x 26E light buoy. The 10-watt Sr/sup 90/ thermoelectric generator, the d-c-to-d-c converter, batteries and the method of installation in the light buoy are describcd. The SNAP 7A generator was fueled with four capsules containing a total of 40,800 curies of Sr/sup 90/ titanate. After fueling and testing, the SNAP 7A electric generating system was … more
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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A Theoretical Study of Destructive Nuclear Bursts in Fast Power Reactors

Description: The calculation of destructive nuclear bursts in fast reactors by an improved Bethe-Tait method, which, for purposes of calculation, neglects propagation of the pressure wave is described. TMen exact numerical calculations for hydrodynamic and neutronic conditions during the power burst are performed in order to assess the importance of this neglect. (auth)
Date: February 1, 1962
Creator: Jankus, V. Z.
Partner: UNT Libraries Government Documents Department
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Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report, October 1-December 31, 1961

Description: The irradiation testing program involving enriched UO/sub 2/ capsules fabricated by low-temperature sintering was continued. Flux monitor data indicate an average burnup level in the capsule of 5800 Mwd/t compared with 9100 Mwd/t calculated. Preparation of 5 different high-purity UC irradiation test specimens of 12% enrichment is reported. Bescriptions of UC preparation procedures by the propane reaction and by skull melting are included. (J.R.D.)
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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SALT PHASE CHLORINATION OF REACTOR FUELS. III. CATALYZED DISSOLUTION OF URANIUM DIOXIDE IN LEAD CHLORIDE-CHLORIDE SYSTEMS

Description: The rapid dissolution of uranium dioxide is described, wherein copper is added to molten lead chloride at 550 deg C. and chlorine is passed through the melt. The integral dissolution of zirconium-clad uranium dioxide fuels is also described. The dissolution rate of uranium dioxide is directly proportional to the concentration of cuprous chloride if an excess of chlorine is used; the value for the rate constant is approximately 100 mg (UO/sub 2/) cm/sup -2/ min/sup -1/ (CuCl molality). The urani… more
Date: February 1, 1962
Creator: Vander Wall, E. M.; Bauer, D. L. & Hahn, H. T.
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Technology Status of the Art Report. Volume I. Heat Transfer and Hydraulics

Description: >Information on heat transfer and hydraulics pertinent to the design and operation of boiling water reactor power plants is presented. The following areas of discussion are covered: heat transfer, two-phase density studies, twophase pressure drop, critical heat flux and burnout, boiling stability, calculation procedures for boiling systems, and thermal-hydraulic design procedures for boiling water reactors. (M.C.G.)
Date: February 1, 1962
Creator: Lottes, P.A.
Partner: UNT Libraries Government Documents Department
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