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Organic Nuclear Reactors: An Evaluation of Current Development Programs

Description: Organic reactor technology is critically evaluated and areas of research and development work now lacking or inadequate for the successful development of this reactor concept are indicated. The development programs for present organic and heavy water moderated concepts appear generally adequate to reach specific goals. However, the narrow scope of the organic reactor program should be broadened to assure coverage of areas where the application of novel principles might result in marked economic… more
Date: May 1, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Material Buckling Measurements on Graphite-Uranium Systems at Hanford: A Summary Tabulation

Description: Measurements of material bucklings for graphite uranium systems are summarized. A comprehensive listing and guide to the original data sources is provided. Complete information on physical and nuclear properties of the lattice and the geometry of the exponential assembly is included, along with some of the auxiliary data taken. The fuel sizes vary from 0.925 to 2.5 in. in diameter for five different fuel geometries. The lattice spacings vary from 4 3/16 to 15 in. Over 300 measurements of materi… more
Date: May 1, 1961
Creator: Wood, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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LABORATORY DEVELOPMENT OF A CARRIER-PRECIPITATION PROCESS FOR THE RECOVERY OF STRONTIUM FROM PUREX WASTES

Description: Strontium recovery from Purex 1WW was investigated with simulated feeds and tracer activities. Initial experiments demonstrated recovery of over 70% of the strontium by sulfate precipitation from partially neutralized 1WW by either increasing the sulfate concentration to about 3 M or by adding carriers such as lead. Precipitation of iron was avoided by addition of one or more moles of tartrate per two moles of iron. Precipitation at elevated temperatures and addition of lead after pH adjustment… more
Date: May 1, 1961
Creator: Bray, L.A. & Van Tuyl, H.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Critical Studies of Dilute Carbide Fast Reactor Core. ZPR-III Assembly 34

Description: Critical studies were made with a simulated, large, dilute power reactor having uranium carbide as fuel. The uranium in the core was 30.7% enriched, and the atomic ratio of uranium to carbon was 0.946. The critical mass was 503.01 kg U/sup 235/ and the critical volume 574.47 liters. Central reactivity coefficients, effective fission crosssection ratios, heterogeneity effects, reactivity worth of distributed materials, foil irradiations, and the average prompt neutron lifetime were measured. Mul… more
Date: May 1961
Creator: Hubert, R. J.; Long, J. K.; McVean, R. L. & Gasidlo, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Fluid-Bed Calculation of Radioactive Waste

Description: Liquid radioactive wastes are converted into solids, with volume reduction factors of 3 to 8, by flash drying on finely screened, porous, inert solid particles (e.g. alumina) in a fluidized bed at 320 to 550 deg C. The wastes may be either aluminum nitrate-containing wastes from the processing of MTR-type fuel elements, or Purex Process wastes. Ruthenium is found to be the only volatile fission product in this temperature range. Methods are described for its removal from the fluidizing gas. (T.… more
Date: May 1, 1961
Creator: Loeding, J. W.; Carls, E. L.; Anastasia, L. J. & Jonke, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL APPARATUS AND TECHNIQUES FOR HIGH TEMPERATURE COMPATIBILITY STUDIES

Description: The development of apparatus and laboratory techniques for the study of materials compatibility with 1500 to 2200 deg F potassium was attempted. Techniques for corrosion tab preparation, dry box capsule filling and sampling, and vacuum filling and sampling are described. Apparatus for rotating capsule testing to 2000 F, rotating capsule testing to 2400 deg F, and anisothermal see-saw'' capsule testing is also described. (auth)
Date: May 31, 1961
Creator: Smith, W.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Steady State Load Tests. Test Results T-554927

Description: Tests were performed to obtain station performance data at various steady-state generator loads. The station 0 was operated for four-hour periods at steady state conditions and levels of 5, 21, 42, and 61 Mw gross generator output. The various readings are presented in tabular form. A list is given of equipment in service during the test. All plant components operated satisfactorily during the test. (M.C.G.)
Date: May 26, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report on the Brookhaven High Flux Beam Research Reactor

Description: The High Flux Beam Reactor, HFBR, is cooled, moderated, and reflected by heavy water and designed to produce 40 Mw with a total epithermal flux of ~1.6 X 10/sup 15/cm/sup -2/ sec/sup -1/ and a flector thermal maximum flux of 7 X 10/sup 14/ cm/sup -2/ sec/sup -1/, using a core formed by ETR plate-type fuel elements in a close-packed array. The hazards summary is given in terms of site description, reactor design, building design, plant operation, disposal of radioactive wastes and effluents, and… more
Date: May 1, 1961
Creator: Hendrie, J. M. & Kouts, H. J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CORE REMOVAL COOLING SYSTEM-SECTION II. CORE I, SEED I. Test Results T- 641113. Section 2

Description: A test was performed on June 19, 1959 to determine the capacity of the Core Removal Cooling System for removing reactor decay heat under split-flow'' conditions. The system operated satisfactorily during this test; the pumps developed a flow of approximates 73 gpm at a total head of 254 ft water, as compared with their rated capacity of 75 gpm at a total head of 250 ft water. (D.L.C.)
Date: May 19, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PM-1 TASK 5, SUBTASK 5.8--LOCAL BOILING HEAT TRANSFER TESTS. SINGLE TUBE HEAT TRANSFER AND PRESSURE DROP TESTS

Description: A program is described which is devoted to heat transfer and pressure drop measurements on single tube sections with coolant flow only on the inside. The tests were conducted on simulated PM-1 fuel elements. Data are included and data reduction methods are discussed. (J.R.D.)
Date: May 1, 1961
Creator: Frank, S.; Jicha, J. & Norin, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Critical Studies of a Dilute Oxide Fast Reactor Core (ZPR-III Assembly 30)

Description: BS>Critical studies of a fast reactor core containing a simulated oxide fuel having an oxygen-uranium atomic ratio of 1: 1 are described. Calculated and experimental critical masses are compared. Experimental results are given for fission ratio, central reactivity coefficient, fuel bunching, and distributed worth measurements. (auth)
Date: May 1961
Creator: Amundson, P. I.; Hess, A. L.; Keeney, W. P.; Long, J. K. & McVean, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MOUND LABORATORY MONTHLY PROGRESS REPORT FOR MAY 1961 ON PLASTICS, RADIOELEMENTS, ISOTOPE SEPARATION, AND REACTOR FUELS

Description: tems were cast and cured. Results of chemical tests on aa epoxy curlang exudate are included. Comparison of solvent effects on retention of radioelements by stainless steel was started and data are tabulated for Ac/sup 227/, Th/sup 227/, a nd Ra/sup 22//sub 3/. Work on protactinium was resumed after suspension of this project in 1960. Methods for preparation of small quantities of highly enriched U isotopes are being examined. Included in the survey are chemical exchange, electromagnetic separa… more
Date: May 30, 1961
Creator: Eichelberger, J.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Research and Development Studies on Waste Storage Process

Description: The basic objectives of this program were the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide. To accomplish these objectives, a literature survey was flrst made of available physical and chemical data for the oxides and nitrates of Cs, Sr, Ru, Zr, Nb, and Ce. The data were supplemented by a calculation of thermodynamic functions for RuO/sub 4/ vapor from the experimentally determin… more
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Flood Safety of the Mixed Spectrum Superheater

Description: Calculations are presented which show that the reactivity effect of flooding and unflooding the fast superheating section of the Mixed Spectrum Superheater can be made small by the addition of epithermal poisons to the superheater. The reactivity effects of flooding superheater sections ranging in size from 1.25 to 3.5 ft cubes and containing U/sup 23/5/sup >/oxide or Pu/sup 239/ oxide fuel and various amounts o f the epithermal poison europium were calculated. Reactivity changes during several… more
Date: May 25, 1961
Creator: Reynolds, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A STUDY OF RESONANCES OF THE Z-7r SYSTEM

Description: Recently a T = 1 resonance in the {Lambda}-{pi} system called Y{sub 1} has been observed with a mass of 1385 MeV. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the {Lambda}-{pi} and {Sigma}-{pi} systems predicted by global symmetry, corresponding to the (3,2/ 3/2) resonance of the {pi}-N system, (2) a spin-1/2 Y-{pi} resonance resulting from a bound state in the {bar K}-N system. The position and… more
Date: May 23, 1961
Creator: Alston, M.H.; Alvarez, L.W.; Eberhard, P.; Good, M.L.; Graziano,W.; Ticho, H.K. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys: Monthly Report 12, April 1961

Description: Monthly report the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between April 1 to April 31, 1961 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: May 4, 1961
Creator: Weinstein, Daniel & Holtz, F. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Magnetic Properties of Insulators : Quarterly Report No. 1 Covering the Period from February 15, 1961 to May 15, 1961

Description: "The magnetic properties of color centers were studied to obtain information regarding electron traps in insulators. Experiments designed to determine the equation governing the recovery of resonance after saturation were carried out. Relatively large samples were prepared by the method of additive coloration. KCl and RbCl crystals were used. Resonance saturation as a function of concentration was investigated and no significant dependence found. Measurements of the unsaturated susceptibility w… more
Date: May 29, 1961
Creator: Markham, Jordan J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazard Analysis for Cesium Shipments

Description: The rail shipment of large quantities of radiocesium involves a potential accidental release of this material in a readily available form to the biosphere. The magnitude of the associated potential damage to man and his environment is evaluated in this report. The evaluation of the consequences of an accidental release of Cs-137 from the Shielded Transfer Tank, Model II (STT) assumes loss of Cs-137 to the atmosphere or to surface-water. Release to the atmosphere could result from a collision fo… more
Date: May 11, 1961
Creator: Watson, E. C.; Junkins, R. L. & Fuquay, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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