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BAND-1--A DATA REDUCTION PROGRAM FOR THE IBM-704

Description: BAND-1 is an IBM-704 program to reduce the experimental data obtained from measurements of the neutron activation distribution within a critical facility. The data reduction consists of correcting the measured data, sorting and ordering it, and calculating the critical buckling parameters by means of a least squares analysis. (auth)
Date: May 1, 1961
Creator: Anderson, B.L.; Hemphill, A.P.; Jarvis, P.H. & Kettler, R.E.
Partner: UNT Libraries Government Documents Department
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BEVATRON OPERATION AND DEVELOPMENT. XXVIII. Period Covered November 1960-January 1961

Description: The Bevatron operated an average of 80% of the scheduled operating time with the exception of one 5-day shutdown period for emergency maintenance of the motor generator sets. The machine was shut off l9% of the scheduled operating time because of component failure and 1% at the request of the user. During and following the Christmas shutdown period an ultrasonic inspection was made of the flywheel keyway on each of the motor generator sets. No faults were apparent. Charpy samples were taken fro… more
Date: May 1, 1961
Creator: Hartsough, Walter D. & Salsig, William W.
Partner: UNT Libraries Government Documents Department
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Carrier-Free Separation Of Hafnium From Rare-Earth Oxides

Description: A carrier-free separation of hafnium from several hundred milligrams of rare earth oxides by anion exchange from saturated HC1 solution is given. The procedure is completed in 4-8 hours and is suitable for remote control work.
Date: May 1961
Creator: Tocher, Mab I. & Hollander, Jack M.
Partner: UNT Libraries Government Documents Department
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Colorimetric Determination of Uranium (IV)

Description: A colorimetric method was developed for the determination of uranium(IV) in the presence of uranium(VI), nitric acid, hydroxylamine sulfate, and hydrazine. A coefficient of variation of 2.4% (n = 25) was obtained. (auth)
Date: May 1, 1961
Creator: Dorsett, R. S.
Partner: UNT Libraries Government Documents Department
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CONCENTRATION OF SETTLED BEDS OF THORIA SLURRY

Description: The variation in concentration of settled beds of flocculated aqueous suspensions of thoria was studied experimentally as a function of the calcination temperature and particle size of the thoria, the temperature and initial concentration of the suspension, and the concentration of added chromic acid. Values of the ultimate settled-bed concentration were obtained by several methods. Dilatant-plastic behavior of one suspension was considered responsible for the formation, in long vertical tubes,… more
Date: May 1, 1961
Creator: Eissenberg, D.M.
Partner: UNT Libraries Government Documents Department
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CORRELATION OF URANIUM ALPHA SURFACE CONTAMINATION, AIR-BORNE CONCENTRATIONS, AND URINARY EXCRETION RATES

Description: ABS>A statistical evaluation is presented of field data including measurements of alpha activity on work surfaces, in the environmental air; and the results of urinalyses obtained from employees assigned to a UF/sub 6/ manufacturing facility. Two years are studied wherein personnel were subject to relatively low concentrations of both soluble and insoluble normal uranium compounds. Approximately 700 urine specimens were collected and 500 spot-air samples, 4000 shift-length air samples, and 24 s… more
Date: May 1, 1961
Creator: Schultz, N.B. & Becher, A.F.
Partner: UNT Libraries Government Documents Department
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COUNTING METHODS FOR THE ASSAY OF RADIOACTIVE SAMPLES

Description: A guide is presented for problems involved in counting methods and techniques used in avoiding or correcting . them. Beta, alpha, and gamma counting is treated. Among the items discussed are the geometry factor, absorption, scattering, and background. A bibliography of 164 references is included. (D.J.C.)
Date: May 1, 1961
Creator: Steinberg, E.P.
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.
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.
Partner: UNT Libraries Government Documents Department
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DESIGN AND HAZARDS SUMMARY REPORT, BOILING REACTOR EXPERIMENT V (BORAX V)

Description: Design data for BORAX V are presented along with results of hazards evaluation studies. Considcration of the hazards associated with the operation of BORAX V was based on the following conditions: For normal steady-state power and experimental operation, the reactor and plant are adequately shielded and ventilated to allow personnel to be safely stationed in the turbine building and on the main floor of the reactor building. The control building is located one- half mile distant from the reacto… more
Date: May 1, 1961
Partner: UNT Libraries Government Documents Department
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Design of the Argonne Low Power Reactor (Alpr)

Description: A description is given of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar statibns north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, naturalcirculation boiling water reactor, ccoled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly from the reactor t… more
Date: May 1, 1961
Creator: Grant, N. R.; Hamer, E. E.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al.
Partner: UNT Libraries Government Documents Department
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Design of the Argonne Low Power Reactor (ALPR)

Description: Report containing "[a] description (...) of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar stations north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, natural-circulation boiling water reactor, cooled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly… more
Date: May 1961
Creator: Hamer, Eberhard E.; Grant, N. R.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al.
Partner: UNT Libraries Government Documents Department
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Development of a Gas Injector System for Homogeneously Labeling Gas Storage Reservoirs

Description: "The laboratory experiments and field testing which were carried out in the development of a homogeneous gas labeling device are described. Detailed drawings of the injector and its most critical components are included. Recommendations are made for a production model of the device along with estimated costs of construction."
Date: May 1, 1961
Creator: Sewell, Curtis & Schulz, Isidor
Partner: UNT Libraries Government Documents Department
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Development of a Variable Orifice for HNPF Fuel Channels

Description: Control of the exit temperature of the coolant from each fuel channel of the Hallam Nuclear Power Facility reactor is obtained by adjusting the coolant flow rate by a remotely operated variable orifice. Two variable orifices were designed and the hydraulic characteristics determined. Both orifice designs utilized a tapered plug moving in and out of a restricted flow passage at the upper end of the fuel channel. Data were obtained on pressure drop as a function of flow rate at different orifice … more
Date: May 1, 1961
Creator: Baroczy, C. J.; Hagel, J. A. & Leonard, W. D.
Partner: UNT Libraries Government Documents Department
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Diffusion in Uranium, Its Alloys, and Compounds

Description: ABS>A review of laboratory diffusion studies on uranium and its compounds and alloys is presented. Included are results and analysis of studies on diffusion in single-phase and in multiphase U alloys, diffusion of gases in U, and diffusion in UO/sub 2/. (J.R.D.)
Date: May 1, 1961
Creator: Rothman, S. J.
Partner: UNT Libraries Government Documents Department
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ELECTRICAL RESISTANCE STUDIES OF ANODIC AND CORROSION OXIDE FILMS FORMED ON ZIRCONIUM

Description: Oxide films were prcduced on Zr and Zr-Ti alloys by anodizing and by exposure to 02 and H20 at high temperatures. The electrical resistances of the films were measured in air at room temperature and in vacuum at temperatures up to 290 deg C. At room temperature, all films were insulators, although anodic films had the higher resistivities. Upon heating corrosion fiIms to 185 and 290 deg C, they became semiconducting. Corrosion films on Zr alloys containing 0.05 to 0.50 wt% Ti had relatively con… more
Date: May 1, 1961
Creator: Misch, R.D.
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.
Partner: UNT Libraries Government Documents Department
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Flux and Temperature Peaking Effects Resulting From the Use of Seamed Fuel Tubes in CP-5

Description: The flux pesking facter resulting from the use of a seamed fuel thimble in CP-5 was determined experimentally and by diffusion theory calculations. A comparison of the two methods indicates that an underestimation of the magnitude and sharpness of the flux peak is obtained from the diffusion calculations. Based on this comparison, a conservative calculation of the peaking effect which would result from the use of seamed fuel tubes in CP-5 indicates a maximum local power-peaking factor of 1.10 a… more
Date: May 1, 1961
Creator: Moon, D. P.
Partner: UNT Libraries Government Documents Department
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