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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 from the inspection bore in the flywheels. Subsequent"vee notch" Charpy impact tests indicated that the flywheels are operated in a brittle region rather than in the ductile range expected. The research program again was devoted mainly to study of pi - and K-meson interactions. (auth)
Date: May 1, 1961
Creator: Hartsough, Walter D. & Salsig, William W.
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, of intractable plugs. (auth)
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 surface surveys were made. Statistical correlations of these data are presented, and a method is proposed for estimating the exposure potential of employee groups working in environments having varying uranium concentrations. (auth)
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. 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.
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 reactor building. For special, hazardous experiments, personnel are withdrawn from the reactor area. (M.C.G.)
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 to a conventional turbine-generator to produce electric power (300 kw nominal) and space-heating (400 kw) requirements consistent with rigid mechanical and structural specifications prescribed by the military, and dictated by the extreme geophysics prevailing at the ultimate site. The over all design criteria emphasize: simplicity and reliability of operation and maintenance, with minimum supervision; minimum on-site construction; maximum use of standard components; limited water supply; utilization of local gravel for biological shielding; transportability by air lift; and nominal 3-year fuel operating lifetime per core loading. The "packaged" concept is incorporated for the initial erection. The plant is not designed for relocation. The design criteria for the prototype necessitate special features. The fuel plates are clad with an alurninurn-nickel alloy (X8001). Burnable-poison (BIO) strips are mechancally attached to the fuel assemblies to compensate the excess reactivity required for a nominal 3-year core operating lifetime. The control rods are actuated by rackand-pinion drive extensions which incorporate rotary seals. Fuel exchange is accomplished without the removal of the pressure vessel head. The electrical power generated is used to operate plant auxiliaries; the "net electric power" is dissipated by resistors. The hot water for space heating is heated in a heat exchanger by 20-psig steam, use being made of the latent heat of vaporization, and all the heat is dissipated by a finned-tube, air-cooled …
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 from the reactor to a conventional turbine-generator to produce electric power (300 kw nominal) and space-heating (400 kw) requirements consistent with rigid mechanical and structural specifications prescribed by the military, and dictated by the extreme geophysics prevailing at the ultimate site. The over-all design criteria emphasize: simplicity and reliability of operation and maintenance, with minimum supervision; minimum on-site construction; maximum use of standard components; limited water supply; utilization of local gravel for biological shielding; transportability by air lift; and nominal 3-year fuel operating lifetime per core loading." (p. 15)
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 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 plug positions; all measurements were made using water, and data were converted to equivalent values for sodium. Either type of orifice was capable of adjusting flow rate to match the power output of a fuel element at any location in the reactor core. The temperature sensitivity (change in exit temperature per unit change in orifice plug position) of the first type of orifice was low (lO deg F/in.) when used in combination with a central fuel element, and high (7OO deg F/in.) when used with a peripheral element. The temperature sensitivity of the second type was more uniform (varying from 90 to 250 deg F/ in.). Consequently, the second type of orifice was selected for the HNPF. (auth)
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 constant resistsnces, although the corrosion rates increased rapidly in this range and the films showed potential differences. For Zr alloys containing 10 to 95 wt% Ti, the film resistances decrease with Ti content amd potential differences were absent in most cases. The results indicate the measurements of the electrical properties of the corrosion films should be made during corrosion. (D.L.C.)
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.F.H.)
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 and a maximum fuel surface temperature 3 deg C above that obtained with extruded tubes for the same total reactor power and the same flow conditions. (auth)
Date: May 1, 1961
Creator: Moon, D. P.
Partner: UNT Libraries Government Documents Department
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HALLAM CRITICAL EXPERIMENT

Description: The results of a critical-experiment program conducted to study the Hallam Nuclear Power Facility (HNPF) reactor concept and to verify design parameters are presented. Experimental procedures and results are given, and comparisons are made with calculational techniques currently in use for determining the nuclear characteristics of the HNPF reactor. (auth)
Date: May 1, 1961
Creator: Doyas, R.J.
Partner: UNT Libraries Government Documents Department
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