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Nuclear Parameter Survey of Molybdenum-Uranium Alloy Fuels for the Sheldon Reactor

Description: A parameter survey was conducted on 19-rod fuel clusters using 3 and 10 wt.% Mo--U alloys. Graphs are included for the core diameter and initial conversion ratio for k/sub eff/= 1.064 as a function of moderator can size, and for the effect of the Mo resonance integral. (D. L.C.)
Date: March 28, 1958
Creator: Blaine, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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P-P Elastic and Charge-Exchange Scattering at about 120 Mev

Description: Observation of antiprotons in a propane or hydrogen bubble chamber offers the possiblity of studying several phenomena for which counter or photographic emulsion techniques are less suitable. Because there is a high ratio of pions, muons, and electrons to antiprotons in the available momentum-analyzed beams, these beams cannot be used in the bubble chamber without an initial purification, which increases the ratio of antiprotons to other particles. Such a purification has been achieved by utili… more
Date: March 28, 1958
Creator: Agnew Jr., Lewis; Elioff, Tom; Fowler, William B.; Gilly, Louis; Lander, Richard L.; Oswald, Larry et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEPOSITION OF GAMMA-RAY HEATING IN STRATIFIED LEAD AND WATER SLABS

Description: Typical results are given from a calculation of the deposition of heat in stratified lead and water slabs caused by a monodirectional, monoenergetic beam of gamma rays incident on the slabs. A total of 512 cases were calculated for infinite slabs with finite thicknesses of 1, 2, 4, and 6 mean free paths; source energies of 1, 3, 8, and 10 Mev, and source angles of incidence which were chosen to give slant slab thicknesses of 1, 2, 3, and 4 times the normal thickness. The results were fitted to … more
Date: July 28, 1958
Creator: Bowman, L. A. & Trubey, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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COMPARISON OF GASES FOR USE AS THE COOLANT IN A GAS-COOLED REACTOR

Description: The expression STAM(Pr) /sup 2/3//(M Cp)/sup 3/! which is often used to compare the merits of various gas coolants is derived and the errors involved in using this term are discussed. An example using CO/sub 2/ and He is shown to illustrate the difference between the true pumping power required and that predicted by the above expression. (auth)
Date: April 28, 1958
Creator: Samuels, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Report No. 52 for December 1, 1957 Through February 28, 1958

Description: Some approximate values of the concentrations of the chlorine ion and the mean activity coefficients of HCl in Dowex 50, as functions of the mean activity of HCl are given. The KCl uptake by anion-exchange resins, Dowex 1 and 2, is plotted. Ion-exchange phase properties of HCl were determined from freezing point measurements. The thermodynamic acid dissociation constants of HClO/sub 4/, HCl, HNO/sub 3/, HBr, and HGaCl/sub 4/ in water-saturated bis(2- chloroethyl) ether, were obtained from coudu… more
Date: February 28, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Corrosion of Type 347 Stainless Steel in Boiling Digest Liquors

Description: Corrosion studies indicate that digest liquors presently in use at the Mallinckrodt Uranium Refining Center should not be excessively corrosive to the digesters, which are constructed of Type 347 stainless steel. Experimental tests have shown that the digest liquors resulting from some of the more recent sources of uranium concentrates might become corrosive if the fluoride, chloride, or free nitric acid contents of these liquors should reach abnormal levels. If such constituents are present, t… more
Date: January 28, 1958
Creator: Fink, F. W.; Braun, W. J. & Stewart, O. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRELIMINARY DESIGN DATA FOR A CIRCULATING FLUORIDE-FUEL-HIGH FLUX REACTOR

Description: A rough calculation shows that a flux of 10/sup 16/ n/cm/sup 2/ sec can be obtained in the internal thermal column (island) of a reflector-moderated circulating fluoride-fuel reactor. Existing NaZrF/sub 5/ base fuels and a graphite moderator are used. The average power density in the reactor is 1 kw/ cc, and the total pcwer is 444 Mw. Inner radius of the fuel region is 50 cm. (auth)
Date: January 28, 1958
Creator: Ergen, W.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Multigroup Diffusion Equations of Reactor Physics

Description: The partial differential equations of the multigroup diffusion model of reactor physics are shown to have solutions both in the time-independent and timedependent problems, and the usually assumed behavior of these solutions is shown to be mathematically valid. The method of spectral representation is developed for the multigroup diffusion operator. (auth)
Date: July 28, 1958
Creator: Habetler, G.J. & Martino, M.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety Device Tests in KEWB I

Description: The feasibility of the electronic-explosive safety device was demonstrated in KEWB-I reactor excursions. It was shown to be a fast, efficient safety system for reactor protection. The safety devices inserted 1.5% negative reactivity into the core region of the KEWB-1 reactor to produce rapid shutdown. The system response time, i.e., that time interval between trip and insertion times, was found to be 4.2 msec. The complete freedom in choice of trip level and the flexibility of device geometry m… more
Date: January 28, 1958
Creator: Weeks, C. C. & Fitch, S. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HEAT TRANSFER TO A BOILING LIQUID MECHANISM AND CORRELATIONS. Progress Report No. 7 (58-40)

Description: Various heat transfer mechanisms which have been previously proposed are analyzed in the light of recent experiments. Evidence is presented in favor of a liquid-vapor exchange mechanism and against the widely accepted "micro-convection" mechanism. The vapor-liquid exchange rnechanism is shown to explain the insensltivity of boiling heat flux to the level of subcooling. A "Reynolds Analogy" for nucleate boiling is presented in some detail. A procedure is given for calculating the superheat at wh… more
Date: May 28, 1958
Creator: Forster, K. & Greif, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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METALLURGICAL EXAMINATION OF VALVE TRIM FROM HRP DUMP VALVE TEST LOOP

Description: An investigation of trim from the HRP Dump Valve Test Loop revealed that performance improved with increasing poppet hardness. From this it was hypothesized that deformation of softer poppets increased the poppet-seat contact area, thus reducing the closing pressure. The deformation areas of a number of poppets were measured and the closing pressures calculated. A plot of closing pressure against leak rate showed a fair correlation and tends to support the hypothesis. (auth)
Date: May 28, 1958
Creator: Cooke, F.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A THREE-STAGE RESEARCH MASS SPECTROMETER

Description: A three-stage mass spectrometer that utilizes two consecutive magnetic focusing;lenses of 20-in. radii followed by a 20-in. radius-of-curvature electrostatic analyzer is described. An abundance sensitivity of 1010 was measurcd for this instrument in the low mass region. Application of this instrument to analytical and research problems in the field of mass spectrometry and the results obtained are discussed. (auth)
Date: May 28, 1958
Creator: White, F.A.; Rourke, F.M. & Sheffield, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EXAMINATION OF CORE ACCESS FLANGE SPECIMEN AND SCALES FROM HRE-2 AFTER RUN 16

Description: Observations, weight data, and chemical analyses of scales on the core access flange and attached specimen assembly exposed in HRE-2 during reactor runs 15 and 16 are reported. The stheinless steel specimen showed a very small weight loss. All surfaces exposed to the reactor solution were covered with an unusual two-layer scale. (auth)
Date: October 28, 1958
Creator: Olsen, A.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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STRESS ANALYSIS OF CONICAL SHELLS

Description: The fundamentals for the stress analysis of conical shells by use of the classical small-deflection theory have been presented in various texts, but before the development of the high-speed computing machines it was not feasible to present the anaylsis in a convenient and usable form. With the aid of these high-speed machines, all necessary functions can be evaluated by the fundamental analyst and tabulated in a convenient form for use by tbs design engineer. It in the intent of this report to … more
Date: August 28, 1958
Creator: Stanek, F.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PAR Loop Schedule Review

Description: The schedule for the installation of the PAR slurry loop experiment in the ·South Facility af the ORR has been reviewed and revised. Changed design philosophy to include maintainability of the loop auxiliaries required extension of the main construction period to the end of,June, with a three month period ending in September, for test and run in during which construction will be completed.
Date: February 28, 1958
Creator: Schaffer, Jr. & W.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further studies on the recovery of fission products and uranium from Purex 1WW

Description: The recovery of fission products from Hanford wastes has for some time been under investigation by various HAPO workers. Flowsheets for the recovery of cesium have been demonstrated, and one for the recovery of cerium is ready for full-level testing. Several tentative flowheets have also been proposed for the recovery of other fission products and of waste plutonium and uranium. The {open_quotes}Integral Flowsheet{close_quotes} developed by Chemical Research Operation is based primarily on the … more
Date: January 28, 1958
Creator: McKenzie, T. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100-Mw Nuclear Power Plant Utilizing a Sodium Cooled, Graphite Moderated Reactor

Description: The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-cooled graphite-moderated reactor with stainless- steel clad. slightiy enriched UO/sub 2/ fuel. The reactor is provided with three main coolant circuits, and the steam cycle has three stages of regenerative heating. The plant control system allows automatic operation over the range of 20 to 100% load, or manual operation at all loads. The site, reactor, sodium systems, reactor auxiliaries, fuel ha… more
Date: February 28, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE DETERMINATION OF NIOBIUM IN URANIUM NIOBIUM ALLOYS

Description: The niobium-uranium alloy is dissolved in hydrofluoric nitric acids and the fluoride removed by fuming sulfuric acid. The niobium is hydrolyzed in an acid-sulfur dioxide medium and converted to niobic oxide by ignition at 900 deg C. The method covers the determination of niobium in niobium-uranium alloys having a niobium content of 8 to 12%. Metals which hydrolyze readily in dilute acid solutions interfere with the determination. (auth)
Date: February 28, 1958
Creator: Goward, G. W.; Reinhold, T. M. & Wiederkehr, V. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DURATION OF ATOMIC COLLISIONS. A NOTE ON RECOMBINATION RATE THEORY

Description: A mechanical treatment of atomic recombination reactions is developed for the case in which the reaction is considered to involve an intermediate excited molecule which is stabilized on collision with any third body. An explicit rate calculation is given for the reaction I + I + A yields I/sub 2/ + A Results are compared with those obtained by treating other models of recombination. The validity of the excited intermediate model and the role of electronic degeneracy are discussed. (auth)
Date: November 28, 1958
Creator: Bunker, D.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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