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The Snap Ii Power Conversion System Topical Report No. 12. Boiler Development

Description: The SNAP II boilers which were designed are summarized. As shown by test results from the three boilers which were tested, a continuous progress in design was achieved. These designs were based on test data from both the SNAP I and SNAP II programs. As the quantity of data increased, physical models describing the heat transfer process were developed. These physical models provide the necessary correlation parameters which permit the extension of existing data to advanced design. Preliminary te… more
Date: July 17, 1961
Creator: Gido, R. G.; Koestel, A.; Haller, H. C.; Huber, D. D. & Deibel, D. L.
Partner: UNT Libraries Government Documents Department
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Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2

Description: The effectiveness of purification in controlling plant radioactivation rates was determined through comparison of the actual effects produced from plant operation with and without purification. With the purification system in service, there was no appreciable difficulty in maintaining the reactor coolant within reference water specifications. In addition, there was no discernible increase of crud deposition in the coolant system as determined by direct radiation measurements of the purification… more
Date: July 21, 1961
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF A PROCESS FOR SODIUM BONDING OF EBR-II FUEL AND BLANKET ELEMENTS

Description: Procedures for assembling EBR-II fuel elements with annular sodium bonds between the uranium rods and the stainless steel claddings are outlined. The results of several meltdown and uranium-settling experiments are given. Bonding experiments were performed: furnace bonding, submerged canning, ultrasonic bonding, centrifuging, pressure pulsing, and vibratory bonding. Vibratory bonding was chosen for the production of the first EBR-II core. (D.L.C.)
Date: July 1, 1961
Creator: Sowa, E.S. & Kimont, E.L.
Partner: UNT Libraries Government Documents Department
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SPERT IV HAZARDS SUMMARY REPORT

Description: Spert IV is a large pool-type experimental facility for reactor kinetic studies. These studies will include power excursion and instability tests for a variety of reactor designs. Since the Spert IV experimental program requires the performance of tests which will approach, and may exceed the threshold of reactor destruction, the probability of occurrence of the maximum possible accident is not negligible compared with that of other possible accidents. The maximum possible accident for this fac… more
Date: July 1, 1961
Creator: Bentzen, F. L. & Crocker, J. G.
Partner: UNT Libraries Government Documents Department
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OXIDATION OF GRAPHITE UNDER HIGH TEMPERATURE REACTOR CONDITIONS

Description: A kinetic study was conducted to provide information on oxidation of reactor graphites in the temperature range of 450 to 675 deg C and on the effects of reactor environment on oxidation rates. Among the parameters studied were chemical reactivity of the graphite, prior oxidation, a high intensity gamma flux during oxidation, variation of the surface-to-volume ratio of the graphite specimens, neutron bombardment prior to oxidation exposure, and gas flow rates. Rate equations showed apparent act… more
Date: July 1, 1961
Creator: Dahl, R.E.
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL MEASUREMENTS OF THE SUCTION HEAD REQUIRED BY THE HALLAM PROTOTYPE FREE SURFACE SODIUM PUMP

Description: Hydraulic tests were made on the Hallam Prototype Free-Surface Sodium Pump to determine the net positive suction head (NPSH) required at various sodium flow rates. Pump performance data were also collected. The results indicate that an NPSH of 22 ft sodium is required at the design flow rate of 7200 gpm at approximates 1000 deg F, agreeing with computed values, and that the pump is designed with a safety margin of slightly over l0%. (D.L.C.)
Date: July 25, 1961
Creator: Atz, R.W.
Partner: UNT Libraries Government Documents Department
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Use Test Comparison of TBP Diluents

Description: Several diluents for possible use in TBP Purex Plant solvent were tested. The tests included nitric --nitrous acid degradation, fission prcduct distribution under simulated plant conditions, emulsillcation, and radiolysis. The order of quality of four diluents is n-dcdecane> Soltrol 170> Shell Code 85030(82000)> Shell E-2342. (D.L.C.)
Date: July 1, 1961
Creator: Mendel, J. E.
Partner: UNT Libraries Government Documents Department
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THE PHYSICS DESIGN OF THE EBR-II

Description: The physics design problems of the EBR-II are summarized. These include analysis of the EBR-II engineering design as well as applicable zero-power critical experiments. Pertinent reactor safety problems are reviewed. Safety considerations bearing on normal plant operation and manipulations within the reactor are emphasized. The implication of controlled in-pile meltdown experiments is considered. Irradiation damage and metallurgical phase phenomena are summarized and related to reactivity. The … more
Date: July 1, 1961
Creator: Loewenstein, W.B.
Partner: UNT Libraries Government Documents Department
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A DESCRIPTION OF INTEGRAL PHYSICS DATA FOR FAST REACTOR DESIGN

Description: Integral physics data for fast reactor design are discussed. The measurements needed include those of critical mass, shape factor, detector ratios, neutron spectra, material replacement experiments, reflector savings, neutron lifetime, Rossi- alpha , and similar quantities. Topics covered include Pu- and U/sup 233/-fueled systems, highly enriched U/sup 235/ systems in optimum geometry, uranium cores of various enrichments and dilutions, extreme geometry critical experiments, specific reactor sy… more
Date: July 1, 1961
Creator: Loewenstein, W.B. & Meneghetti, D.
Partner: UNT Libraries Government Documents Department
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CURRENT STATUS OF THE AC IONIZATION CHAMBER

Description: ABS>The design concept of an a-c ionization chamber and its supporting electronics is described. Several designs are possible and the sensors can be tailored to specific requirements when necessary. Mode of operation, signal voltage development, and switching frequency are discussed. High-sensitivity operation is described. Requirements for high-temperature, power-level operation are outlined. (M.C.G.)
Date: July 1, 1961
Creator: Rusch, G.K.
Partner: UNT Libraries Government Documents Department
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REMOTE DISSOLUTION AND ANALYTICAL PROGRAM FOR IRRADIATED THORIUM

Description: A remote dissolution and analytical program for irradiated thorium is given. The aluminum jacket on the slug was dissolved with 6M nitric acid and 0.005M mercuric nitrate. After a water wash, the thorium dissolution was accomplished with concentrated nitric acid made 0.04M in hydrofluoric acid. Weighing, dissolving, and sampling were done remotely in the multicurie cell at the Idaho Chemical Processing Plant. Handling techniques for weighing and dissolving the slugs are described. Transferring … more
Date: July 14, 1961
Creator: Huff, G. A.; Doggett, I. L.; Fletcher, R. D. & Jacobson, M. E.
Partner: UNT Libraries Government Documents Department
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POWER-TO-VOID TRANSFER FUNCTIONS

Description: Variations in the distribution of steam bubble, the "void" distribution, in a boiling channel as a function of changes in heating power were studied. A rectangular test tube, of 1.11 x 4.44-cm cross section and 127-cm height, was inserted in a forced-circulation pressure loop. The tube was heated by passing an a-c current through the tube walls. A power oscillator was built which could give a 10% peak-topeak sinusoidal power modulation at any frequency in the interval from 0.01 to 10 cps. Varia… more
Date: July 1, 1961
Creator: Christensen, H.
Partner: UNT Libraries Government Documents Department
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CHARACTERIZATION OF UO$sup 2$ POWDERS. Progress Report No. 8, May and June 1961

Description: Correlation of a number of physical and chemical properties of 12 different UO/sub 2/ powders was continued. The UO/sub 2/ powders were studied by means of infrared absorption measurements, oxidation temperatures as determined by hot stage microscopy techniques, and B. E. T. surface area measurements. Additional pellets were prepared to study ceramic performance. (M.C.G.)
Date: July 19, 1961
Creator: Carpenter, J.F.
Partner: UNT Libraries Government Documents Department
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Electrical Properties of Glass. A Bibliography

Description: A bibliography on the electrical properties of glass is presented. The 267 references covering the period from 1930 through 1960 are arranged according to subject. An author index is included. (M.C.G.)
Date: July 1, 1961
Creator: Kepple, R.
Partner: UNT Libraries Government Documents Department
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Structures and Properties of Uranium-Fissium Alloys. Final Report- Metallurgy Program 4.1.23

Description: A study was made of the phase relations and the properties of uranium-- fissium alloys which have compositions bracketing that intpnded for the first core loading of Experimental Breeder Reactor II. The fissium aggregate in the alloys consisted of the elements Zr, Nb, Mo, Ru, Rh, and Pd. Phase relations are shown to parallel closely those in the dominant U--Mo--Ru ternary system. The uranium gamma phase is stabilized down to 552 deg C, while the beta phase is entirely suppressed at high fissium… more
Date: July 1, 1961
Creator: Zegler, S. T. & Nevitt, M. V.
Partner: UNT Libraries Government Documents Department
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Preparation of Uranium(IV) Nitrate Solutions

Description: A procedure was developed for the preparation of uranium(IV) nitrate solutions in dilute nitric acid. Zinc metal was used as a reducing agent for uranium(VI) in dilute sulfuric acid. The uranium(IV) was precipitated as the hydrated oxide and dissolved in nitric acid. Uranium(IV) nitrate solutions were prepared at a maximum concentration of 100 g/l. The uranium(VI) content was less than 2% of the uranium(IV). (auth)
Date: July 1, 1961
Creator: Ondrejcin, R. S.
Partner: UNT Libraries Government Documents Department
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Dynamic Properties of Heterogeneous Water Reactors

Description: The types of tests performed in SPERT-I, and the tests proposed for SPERT-II and -III, are described. These reactors are described, and factors influencing their dynamic behavior are discussed. The tests are classed as static, step, ramp, and oscillatory. The correlation between the test results and the reactor dynamic safety characteristics (stability, self-shutdown under excursion conditions, etc.) is investigated. (T.F.H.)
Date: July 20, 1961
Creator: Forbes, S. G. & Nyer, W. E.
Partner: UNT Libraries Government Documents Department
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THE EXPERIMENTAL BERYLLIUM OXIDE REACTOR. MARITIME GAS-COOLED REACTOR PROGRAM

Description: LIUM OXIDE REACTOR. MARITIME GAS-COOLED The Experimental Beryllium Oxide Reactor, EBOR, will be constructed at the National Reactor Testing Station as the AEC portion of the joint Maritime Administration--AEC Maritime Gas Cooled Reactor Program. The ultimate goal of the Program is the development of nuclear power plants employing a helium cooled and beryllium oxide moderated reactor directly coupled to a closed cycle gas turbine. The objective is to obtain compact nuclear engines suitable for u… more
Date: July 1, 1961
Creator: Moore, W.C.
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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Design Criteria for Steel in Nuclear Reactors

Description: S>Criteria for stress analysis and structural design with steel for the critical components of nuclear plants are presented. An effort was made to integrate the effects on the strength of steel of the coexisting phenomena, such as mechanical and thermal loads, stress cycling and fatigue, creep and creep rupture, irradiation, and loss of ductility. Extensive use of the plastic region of steel was made for the accommodation of thermal stresses. The concept of cumulative damage in the plastic regi… more
Date: July 1, 1961
Creator: Fistedis, S.H.
Partner: UNT Libraries Government Documents Department
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RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report

Description: The study of the formation mechanism of free radicals in polymeric materials was continued. Emphasis was placed on an examination of the effect of structural factors on the efficiency of free-radical site formation in acrylate polymers. Site measurements as a function of dose were made for polymethacrylamide and repeated for polymethacrylic acid. The volatile products from the irradiation of polyacrylic acid. polymethacrylic acid, poly-ter- butylmethacrylate. and polycyclohexyl methacrylate wer… more
Date: July 18, 1961
Creator: Sunderman, D.N. ed.
Partner: UNT Libraries Government Documents Department
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Table of Vibrational Force Constants

Description: Tabulations are included for: vibrational and rotational parameters for diatomic molecules; quadratic, cubic, and quartic vibrational force constants of diatomic molecules; parameters for empirical functibns relating force constants to bond length; and cubic force constants for bond stretching in polyatomic molecules. (B.O.G.)
Date: July 1, 1961
Creator: Herschbach, D. R. & Laurie, V. W.
Partner: UNT Libraries Government Documents Department
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Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Description: Report issued by the APDA over a design study conducted on an "in-pile package loop for use as a reactor fuel test facility" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date: July 28, 1961
Creator: Blessing, W. G.; Balsbaugh, R. R.; Bloomfield, D. E.; Busch, J. S.; Hennig, R. J.; Jens, W. H. et al.
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys Quarterly Report: April - June 1961

Description: Quarterly report documenting progress on a project to determine an improved zirconium alloy for service in superheated water and steam. This report describes the results of approximately 75 compositions that were prepared prior, and presently are being arc-melted and fabricated into corrosion specimens, continuing the investigations of the effect of zirconium purity and heat treatment on corrosion and resistance.
Date: July 11, 1961
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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