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CRITICAL EXPERIMENTS FOR THE PRELIMINARY DESIGN OF THE ARGONNE HIGH FLUX REACTOR

Description: Critical experiments were performed with two assemblies simulating a cold clean, and an end-of-cycle,- Argonne High Flux Reactor, core. Data were obtained for flux distributions; cadmium ratios; temperature and void coefficients; and control rod, beam hole, and reflector worths. The data obtained furnished confirmation of theoretical predictions. The peak 2200-m/sec flux per unit power was measured as 3 x 10/sup 7/ n/(cm/sup 2/)(sec)(watt) for both cores. The two cores had internal H/sub 2/O th… more
Date: June 1, 1961
Creator: de Villiers, J.W.L. ed.
Partner: UNT Libraries Government Documents Department
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Transient Temperature Distributions in a Thermally Orthotropic Plate With Non-Uniform Surface Heating

Description: ent temperature variation in a thermally orthotropic plate which is subjected to an arbitrary heating rate distribution along one face with all other surfaces being insulated. Dimensionless temperature histories and distributions determined from this solution are presented for the special, but representative, case of a linearly varying heating rate distribution on plates with varying degrees of thermal orthotropy. These results establish quantitatively the value of a material with high planar a… more
Date: June 1, 1961
Creator: Hornbaker, David Ross
Partner: UNT Libraries Government Documents Department
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A Theoretical Study of the Transient Operation and Stability of Two-Phase Natural Circulation Loops

Description: Mathematical models of the time-dependent behavior of two-phase natural- circulation loops were used to predict the operation and to explain the unusual instability sometimes observed. The initial results obtained for a loop similar to the Univ. of Minnesota loop were used to formulate a more complex and accurate model, and the predicted transient behavior was in close agreement with the experimental results from the Minnesota loop. For a 300psia, high-pressure loop, unstable oscillatory behavi… more
Date: June 1, 1961
Creator: Garlid, K.; Amundson, N. R. & Isbin, H. S.
Partner: UNT Libraries Government Documents Department
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Periodic Waste Disposal System Material Balance Test. Core 1, Seed 2. Test Evaluation T-641317. Section 1

Description: A test was carried out to determine the adequacy of storage capacity and operating procedures of the radioactive waste disposal system during a normal reactor plant warmup. The capacity and operating procedures were found to be adequate. It was impossible to perform a complete material balance based on existing level instrumentation and using the data required by the test procedure. Approximately 21,290 gal. of waste were received in the system and 13,210 gal. were discharged to the river with … more
Date: June 30, 1961
Partner: UNT Libraries Government Documents Department
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Corrosion Tests in Molten Lead-Lead Chloride

Description: Corrosion tests were run on some commercial grade metals, an alloy steel, stainless steels, chromium-- nickel-iron alloys, nickel base alloys, cobalt base alloys, and a chromium-- nickel-- cobalt-- iron ailoy in the system: leadlead chloride-lead chloride vapor at 528 deg C under an argon atmosphere. The following metals and alloys showed a corrosion rate of nine mils per month or less and did not suffer intergranular or other localized attack: tantalum, Incoloy 804, Hastelloy F, Carpenter-20 (… more
Date: June 1, 1961
Creator: Stolica, N. D.; Adams, G. S. & Bomar, M. R.
Partner: UNT Libraries Government Documents Department
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Experimental and Analytical Reactivity Studies of Clean Critical Stainless Steel Cores

Description: ABS>The results are presented of critical water height measurements made on close-packed lattices of Spert III, highly enriched, plate-type, stainless- steel-clad fuel elements. Experiments were conducted with cores containing no control rods and with cores containing a single, fully-inserted control rod. The "clean critical" data obtained in these experiments were used to test the validity of various aspects of a four-group, diffusion theory analysis of the full scale Spert III reactor. The re… more
Date: June 16, 1961
Creator: Spano, A. H.
Partner: UNT Libraries Government Documents Department
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SNAP 2 PRIMARY SYSTEM TEST-OBJECTIVES, SYSTEM DESCRIPTION, AND PROCEDURES

Description: The SNAP-2 Primary System Test loop fabrication was completed with associated flight prototype components including reactor core and boiler mockups for volume and DELTA P simulation, CRU-IIII NaK pump, compact heater, and expansion compensator. A mobile loading system was designed and fabricated with the capability of cleaning the NaK prior to final loop sealing. Loop descriptions, test objectives, and operating procedures are presented. (auth)
Date: June 12, 1961
Creator: Kikin, G.M.
Partner: UNT Libraries Government Documents Department
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A Small Scale Countercurrent Liquid-Liquid Extractor

Description: Details of design and operation are given for a laboratorysize, 20 - stage, multiple-contact, "unlimited-feed'', countercurrent-flow, liquid-liquid extractor. The apparatus consists mainly of glass parts that are joined by polyethylene tubing and are mounted in a steel cradle that can rotate on its horizontal axis. The reservoirs for feed liquids are an integral part of the assembly, and proper rotation of the assembly causes the flow of liquids to, through and from the extractor. Testing and d… more
Date: June 1, 1961
Creator: Wilhelm, H. A.
Partner: UNT Libraries Government Documents Department
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Dynamic Simulation of Multi-Pass Pressurized Water Nuclear Power Plants by Analog Computer Techniques

Description: A kinetic model of the primary loop of a multi-pass pressurized water reactor power plant is developed to evaluate, by analog computer techniques, the transient response characteristics under conditions of steam generator load and reactor control rod perturbations. Using the 2-pass 28 Mw(t) SM-2 reactor as a typical plant, transient behavior patterns are illustrated and examined for a variety of load inputs, variations in plant constants, and analog model simplifications. (auth)
Date: June 1, 1961
Creator: Brondel, J. O.
Partner: UNT Libraries Government Documents Department
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PROGRAM ODD--A ONE-DIMENSIONAL MULTIGROUP CODE FOR THE IBM-7090 (ANP PROGRAM NO. 657)

Description: The physical and mathematical reactor models which are used in Program ODD are discussed. In addition, the FORTRAN II source program listings, decimal data input sheets, and input and output for a sample case are given. Program ODD was designed to raake use of the Revised Nuclear Data System at ANPD which consists of twenty-five energy group cross-section data including high energy inelastic scattering matrices, resonance parameters for the resolved resonances, and thermalization scattering mat… more
Date: June 30, 1961
Creator: Fischer, P.G.; Wenstrup, F.D. & Hoffman, T.A.
Partner: UNT Libraries Government Documents Department
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A Neutron Diffraction Study of Krypton in the Liquid State

Description: A study was made of the neutron diffraction patterns obtained from Kr liquid under seventeen conditions of temperature and pressure at 117 to 210 deg K. The low temperatures were used because the diffraction patterns and the corresponding radial distribution functions are more sharply defined near the liqdid triple point. (J.R.D.)
Date: June 1, 1961
Creator: Clayton, G.T. & Heaton, L.
Partner: UNT Libraries Government Documents Department
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Preliminary Results of High-Temperature Bare U$sup 235$-C Critical Assembly Measurements

Description: The influence of temperature on the critical buckling or bare graphite assemblies with various carbon-to-uranium235 molar ratios has been measured. A range from l185: 1 to 2l,690: 1 was covered, for 45 to 1205'F. Preliminary results indicate that the fractional rate of change of critical buckling with core temperature varies monotonically with C/U2as ratio by a factor of five over the factor-of-eighteen range in gross C/U2as ratio. This quantity appears to approach asymptotically a value n… more
Date: June 1, 1961
Creator: Finke, R. G.
Partner: UNT Libraries Government Documents Department
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Force Multiplier for Use With Master Slaves

Description: A force multiplier was designed. This piece of equipment was made to increase the gripping force presently available in the Model 8 master slave. The force multiplier described incorporates a clamp which can be quickly attached to and detached from the master slave hand. (auth)
Date: June 1, 1961
Creator: Miles, L. E.; Parsons, T. C. & Howe, P. W.
Partner: UNT Libraries Government Documents Department
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Pressure Drop of Multirod Elements With Helical Spring Spacers

Description: The pressure drop of a new fuel element design concept of spacing rods by means of helical wire springs was investigated experimentally and analytically. Extensive single- and two-phase pressure drop data at 1,000 psia were obtained for one flow geometry and helical spring spacer. Test conditions ranged from 0.7 to 1.2 x 10/sup 6/ lb/hr ft/sup 2/ in mass velocity and from 0 to 15% in quality. The effect of the specific spring which was tested was to increase the over-all pressure drop by 70%. A… more
Date: June 1, 1961
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
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SL-1 ANNUAL OPERATING REPORT, FEBRUARY 1960-JANUARY 3, 1961

Description: >The plant was operated from Feb. l959 until Jan. 3, 1961 when a nuclear excursion rendered the plant inoperable, A summary of operations is presented for the period Feb. 1960 until the incident. Plant operational tinwe during the period was 78% of that available. Satisfactory operation of conventional plant equipment was observed during 196 startups and scrams. An inspection of fuel assemblies after 700 Mwd showed no damage except to the B-Al strips attached to these assemblies. A greater than… more
Date: June 15, 1961
Partner: UNT Libraries Government Documents Department
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Mortality in Small Animals Exposed in a Shock Tube To "Sharp"-Rising Overpressures of 3-4 Msec Duration. Technical Progress Report

Description: A total of 661 animals was exposed to sharp''-rising overpressures of 3 to 4 msec duration using a shock tube of novel design which produced a pressure pulse similar to that obtained with high explosives. The reflected shock overpressures associated with 50% lethality were 29.0, rabbit, respectively. Other observations included the time of death in mortally wounded animals and gross pathological lesions likely to contribute to mortality. Selected data from the literature bearing upon the influe… more
Date: June 15, 1961
Creator: Richmond, D. R.; Goldizen, V. C.; Clare, V. R.; Pratt, D. R.; Sherping, F.; Sanchez, R. T. et al.
Partner: UNT Libraries Government Documents Department
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TWENTY-FIVE GROUP REACTOR NUCLEAR DATA TAPE NEUTRON CROSS SECTIONS

Description: A compilation is presented, in the twenty-five group Reactor Nuclear Data Tape format, of neutron cross sections for elements of major interest for GE- ANPD reactor analysis. The tabulated data are a reproduction of neutron cross section information contained on the Reactor Nuclear Data Tape, which was recently prepared. A brief outline of methods used in processing of the cross sections is also included. (auth)
Date: June 13, 1961
Creator: Zwick, J. W. & Kostigen, T. J.
Partner: UNT Libraries Government Documents Department
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Flux and Power Distributions for the SM-2 Reference and Critical Experiment Cores

Description: A detailed analysis was made of the power distributions in the SM-2 experimental core at 68 deg F and the SM-2 reference core at 510 deg F. This analysis supersedes the power distribution calculations presented in APAE No. 69. The calculated distributions for the experimental core were normalized to measured data wherever possible in order to obtain corrections factors for application to the reference core. The over-all power distributions were calculated by synthesis of one-dimensional axial c… more
Date: June 30, 1961
Creator: Fried, B. E.; Alford, M. R. & Oggerino, J. P.
Partner: UNT Libraries Government Documents Department
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SL-1 Annual Operating Report: February, 1960-January 3, [1961]

Description: The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date: June 15, 1961
Partner: UNT Libraries Government Documents Department
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BIO-ORGANIC CHEMISTRY QUARTERLY REPORT - MARCH THROUGH MAY1961

Description: The study of meteorite Murray has been reported in previous Quarterly Reports. This report gives further results with Murray, and information on another meteorite, Orgueil. A sample of Orgueil was sent from the Museum National d Histoire Naturelle, Paris. It fell in several pieces over an area of 2 square miles near Orgueil, France, in 1864. The elemental analysis of this meteorite is shown in Table 1. They extracted a 10.07-g sample of this meteorite with water, using the same procedure as tha… more
Date: June 29, 1961
Partner: UNT Libraries Government Documents Department
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