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2,451 Matching Results
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Organic Nuclear Reactors: An Evaluation of Current Development Programs
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 benefits. Further work, principally of a basic nature, is recommended in the fields of chemistry, processing, management, and thermodynamic properties of coolants, in fuel development, and in concept evaluation. (N.W.R.)
Date:
May 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A THEORETICAL STUDY OF SIMPLE MANY-ELECTRON SYSTEMS
None
Date:
May 1, 1961
Creator:
Sachs, L.M.
Object Type:
Report
System:
The UNT Digital Library
Material Buckling Measurements on Graphite-Uranium Systems at Hanford: A Summary Tabulation
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 material buckling are included. (auth)
Date:
May 1, 1961
Creator:
Wood, D. E.
Object Type:
Report
System:
The UNT Digital Library
BIOLOGICAL AND MEDICAL RESEARCH DIVISION SUMMARY REPORT, JANUARY-DECEMBER 1960
Separate abstracts were prepared for 43 sections of this report. (C.H.)
Date:
May 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
LABORATORY DEVELOPMENT OF A CARRIER-PRECIPITATION PROCESS FOR THE RECOVERY OF STRONTIUM FROM PUREX WASTES
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 were shown to be beneficial. Strontium recoveries of over 95% were achieved by precipitation at about 80 deg C at pH values of 0.4 to 4.0 with sulfate concentrations of 0.67 to 3 M and over 0.02 M lead carrier added. High sulfate concentrations were required at low pH, but the sulfate concentration is not critical above pH 1. Some separation of strontium from cerium was observed at pH 2 to 4, with the degree of separation being dependent on both tartrate concentration and pH. Recovery of strontium from the sulfate precipitate by leaching with nitric acid, sodium acetate, or oxalic acid was unsatisfactory because of the large volumes required. Metathesis with sodium hydroxide removed most of the lead as plumbite and converted …
Date:
May 1, 1961
Creator:
Bray, L.A. & Van Tuyl, H.H.
Object Type:
Report
System:
The UNT Digital Library
Critical Studies of Dilute Carbide Fast Reactor Core. ZPR-III Assembly 34
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. Multigroup calculations using the Yiftah, Okrent, and Moldauer crosssection set overestimated k for the critical configuration by 4.7%. (auth)
Date:
May 1961
Creator:
Hubert, R. J.; Long, J. K.; McVean, R. L. & Gasidlo, J. M.
Object Type:
Report
System:
The UNT Digital Library
The Fluid-Bed Calculation of Radioactive Waste
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.F.H.)
Date:
May 1, 1961
Creator:
Loeding, J. W.; Carls, E. L.; Anastasia, L. J. & Jonke, A. A.
Object Type:
Report
System:
The UNT Digital Library
EXPERIMENTAL APPARATUS AND TECHNIQUES FOR HIGH TEMPERATURE COMPATIBILITY STUDIES
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.
Object Type:
Report
System:
The UNT Digital Library
Steady State Load Tests. Test Results T-554927
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
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Solid State Neutron Detectors
None
Date:
May 1, 1961
Creator:
Murphy, J. F.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Preliminary Hazards Summary Report on the Brookhaven High Flux Beam Research Reactor
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 safety analysis. (B.O.G.)
Date:
May 1, 1961
Creator:
Hendrie, J. M. & Kouts, H. J. C.
Object Type:
Report
System:
The UNT Digital Library
CORE REMOVAL COOLING SYSTEM-SECTION II. CORE I, SEED I. Test Results T- 641113. Section 2
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
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
PM-1 TASK 5, SUBTASK 5.8--LOCAL BOILING HEAT TRANSFER TESTS. SINGLE TUBE HEAT TRANSFER AND PRESSURE DROP TESTS
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.
Object Type:
Report
System:
The UNT Digital Library
Critical Studies of a Dilute Oxide Fast Reactor Core (ZPR-III Assembly 30)
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.
Object Type:
Report
System:
The UNT Digital Library
MOUND LABORATORY MONTHLY PROGRESS REPORT FOR MAY 1961 ON PLASTICS, RADIOELEMENTS, ISOTOPE SEPARATION, AND REACTOR FUELS
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 separation, gaseous and liquid thermal diffusion, gas centrifugation, and photochemical techniques. Continued investigation of viscosities of La and Pr for use in Pu alcontinued along with studies of Pu bearing glass fibers. (J.R.D.)
Date:
May 30, 1961
Creator:
Eichelberger, J.F.
Object Type:
Report
System:
The UNT Digital Library
Research and Development Studies on Waste Storage Process
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 determined infrared spectrum and the theoretically calculated raman-active fundamentals. Data are presented graphically. (C.H.)
Date:
May 19, 1961
Creator:
Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Object Type:
Report
System:
The UNT Digital Library
Flood Safety of the Mixed Spectrum Superheater
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 postulated flooding processes are given. Methods for deterthination of fissile and fertile material and poison cross sections in the resonance- region are discussed. (auth)
Date:
May 25, 1961
Creator:
Reynolds, A. B.
Object Type:
Report
System:
The UNT Digital Library
[Lightning Storm at Administration Building]
Photograph of a lightning storm at North Texas State University. A streak of lightning can be seen behind the Administration Building.
Date:
May 1961
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library
[Storm at North Texas State University]
Photograph of a thunderstorm at North Texas State University. The Administration building can be seen prominently in the photograph.
Date:
May 1961
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library
[Photograph 2012.201.B0298.0433]
Photograph taken for a story in the Daily Oklahoman newspaper.
Date:
May 5, 1961
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0418.0269]
Photograph taken for a story in the Oklahoma Times newspaper. Caption: "fatigue lines faces during lull"
Date:
May 31, 1961
Creator:
Cobb, Richard
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0234.0469]
Photograph taken for a story in the Oklahoma Times newspaper. Caption: "Pieces hit ceiling. Next shot gets other cup."
Date:
May 17, 1961
Creator:
Matheson, Mandell
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0239.0516]
Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Dave Marr, left and Pete Cooper are in quest of some of the 20,000, plus bonuses, at stake at Burneyville this week."
Date:
May 7, 1961
Creator:
Lucas, Jim
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0295.0340]
Photograph taken for a newspaper owned by the Oklahoma Publishing Company. Caption: "Miss Sharon Davis, (left) of 2817 N.W. 64 St., Oklahoma City, Okla., is shown with AFL- CIO Secretary - Treasurer William F. Schnitzler as h presented the essay contest winner with a gift at a special luncheon at the Willard Hotel in Washington D. C., honoring the winners who turned in the best essays on "Employment of the Physically Handicapped."
Date:
May 17, 1961
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History