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ANALYSES OF THE RADIAL SEPARATOR

Description: A mathematical analysis is presented concerning the performance of the radial or vane type steam separator. The analyses are concerned with the spread of flow on the vanes because of centrifugal force (which requires that the vane height be greater than the nozzle), and with separation of the vapor from the liquid. (J.R.D.)
Date: February 1, 1962
Creator: Robbins, C.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Technology Status of the Art Report. Volume I. Heat Transfer and Hydraulics

Description: >Information on heat transfer and hydraulics pertinent to the design and operation of boiling water reactor power plants is presented. The following areas of discussion are covered: heat transfer, two-phase density studies, twophase pressure drop, critical heat flux and burnout, boiling stability, calculation procedures for boiling systems, and thermal-hydraulic design procedures for boiling water reactors. (M.C.G.)
Date: February 1, 1962
Creator: Lottes, P.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Carbide Fuel Development. Progress Report, September 15, 1961 to December 31, 1961

Description: Single phase, solid solution, UC-PuC powder was synthesized reproducibly from a mixture of the oxides and carbon. A simple method of monitoring the reaction was developed. UC-PuC-0.1 wt% Ni pellets of 93% theoretical density were made reproducibly, with some samples as high as 95% of theoretical denstty. The pellets contain minor amounts of (U,Pu)/sub 2/C/sub 3/ most of the time. Efforts to make reproducible 95%, single-phase material are under way. Microprobe analysis of UC-0.1 wt% Ni specimen… more
Date: February 1, 1962
Creator: Strasser, A. & Taylor, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cesium-137 index for nuclear materials content of coating waste

Description: Cs-137 has been chosen as a possible index of the plutonium and uranium in coating waste. This index is a stable ratio as long as the plutonium formation rate (Pu/MD) is stable. Calculations are presented for Purex and Redox. It is recommended that the Cs-137 index method be used for determining nuclear materials content in coating waste at both Purex and Redox; this will result in higher but more accurate statements of Pu, U losses in coating waste.
Date: February 1, 1962
Creator: Schneider, R. A. & Zimmer, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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COMPONENT FEASIBILITY TEST REPORT FOR THE AMF ON-POWER REFUELING SYSTEM FOR THE DOUGLAS POINT PLANT

Description: Activities in a phase of CANDU I refueling machine development are reported which are concerned with obtaining test data for various system subcomponent parts. The basis for selecting those units requiring test was established through engineering evaluation of available information. Results of tests based on these requirements are included in the form of test reports. (J.R.D.)
Date: February 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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COUNTERCURRENT MUTUAL SEPARATION OF Y$sup 91$ AND Pm$sup 147$ BY SOLVENT EXTRACTION USING PULSE COLUMN

Description: The use of continuous solvent extraction was proved quite satisfactory in separating Y/sup 91/ from Pm/sup 147/, using synthetic mixtures of the nuclide pair on a tracer level. The separation was conducted in a compound perforated plate pulse column using a solvent containing 10% HDEHP, di(2 ethylhexyl) phosphoric acid, in toluene. Flow rates to the extraction column were maintained around 1 ml/min of feed, 3 ml/min scrub and 12 ml/min solvent giving one volume change per hour. Pulse frequency … more
Date: February 1, 1962
Creator: Mandil, M. A.; Mason, G. W. & Peppard, D. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Radiation Contamination Levels During Core I, Seed 2-Seed 3 Refueling Operations. Test Evaluation (T-643128)

Description: A record is presented of radiation contamination levels observed in the work area during the Core I Seed 2-Seed 3 refueling operations. The radiation levels for Seed 2-3 refueling were somewhat higher thand those for Seed 1-2 refueling in certain areas and are ascribed to operations being carried out under dry conditions. Maximum contamination levels were also higher, but the general contamination level was lower. The activity of canal water was higher and characterization was made on some of t… more
Date: February 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Ductile Beryllium Composites

Description: The work of the second year to produce ductile beryllium composites by liquid-phase sintering is reported. Ductility in a predominantly beryllium composite was sought through the attainment of a structure in which beryllium particles are enveloped in a ductile metallic matrix. As the result of the investigation of aluminum-silver binary al!oys, aluminum-40 to 50% silver compositions were added to the silver-5 to 8% aluminum compositions as candidate matrices satisfying the requirenent that the … more
Date: February 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Monthly Progress Letter for Month of January 1962

Description: Development work leading to comparison of co-precipitated and mechanically blended UO/sub 2/-- PuO/sub 2? powders is reported in which special emphasis was placed on blending trials, pellet sintering studies, and subsequent evaluation of pellets made with blended material. Homogeneity studies indicate that currently used procedures are unsatisfactory because particle buildup occurs during blending. Powder preparation via the oxalate route was continued along with PuO/sub 2/ moisture pickup stud… more
Date: February 1, 1962
Creator: Puechl, K.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE DISTORTED-WAVE THEORY OF DIRECT NUCLEAR REACTIONS. I. "ZERO-RANGE" FORMALISM WITHOUT SPIN-ORBIT COUPLING, AND THE CODE SALLY

Description: The distorted-wave theory of direct nuclear reactions is presented in a unified manner, in which the effects of assuming various reaction mechanisms and nuclear models appear only in certain radial form factors. The zero-range approximation is used, and spin-orbit coupling is neglected in the distorted waves. Formulas are given for transition amplitudes, cross sections, and polarizations. A description is given of the IBM-704 computer code SALLY that is based on these formulas. (auth)
Date: February 1, 1962
Creator: Bassel, R.H.; Drisko, R.M. & Satchler, G.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Graphite Chemical Reactivity on Thermal Instability Conditions in Air-Cooled Channels

Description: Conditions leading to thermal instability in air-cooled channels are mathematically expressed. It is shown that thermal instability occurs only if the air temperature approaches the graphite temperature. The length of channel necessary to yield a particular air temperature is derived. The effects of enhanced reactivities on the instability conditions are discussed. (R.J.S.)
Date: February 1, 1962
Creator: Schweitzer, D. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Efficiency of Multiple Traversal Targets

Description: The efficiency of multiple traversal targets is defined as the probability that a proton dies by making a nuclear collision in the target rather than by hitting the limit of the synchrotron aperture. The efficiencies of Be, Al, Cu, and Pb targets are shown for 15 and 30-Bev protons in the Brooknaven AGS. Beryllium was found to be the most efficient. (M.C.G.)
Date: February 1, 1962
Creator: Courant, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Examination of Uranium-2 w/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I. Final Report-Program 6.1.11

Description: Six groups of U-2 wt% Zr fuel slugs were irradiated in the first core of the EBR-I to burnups of 0.080 to 0.189 at.% at calculated temperatures of 307 to 353 deg C. Two groups of cast specimens were found to be more dimensionally stable than four groups of wrought slugs. Of the wrought slungs, the as quenched group showed less tendency to grow than the three groups which had some annealing after quenching. Specimens at burnups of about 0.189 at.% and at 383 deg C showed the onset of swelling as… more
Date: February 1, 1962
Creator: Murphy, W. F.; Klank, A. C. & Paine, S. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final summary of impurities in beryllium oxide as used in the Tory II-A-1 reactor. Pluto technical note No. 257

Description: Declassified 26 Nov 1973.<><DSN>29:020150<ABS>has resulted from a sophisticated consideration of its application as a ramjet engine. An idealized reactor power profile was derived directed toward optimizing the transfer of heat energy to the airstream. Some twenty-six classes of fueled tubes have been used to tailor both axial and radial reactor power profiles accordingly. Procedures for the fabrication of components and assembly of the reactor have consequently become tedious and lengthy to sa… more
Date: February 1, 1962
Creator: Hampel, V. E. & Moran, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Fuel Reprocessing Plant for Fast Ceramic Reactors

Description: A study was made of the adaptation of the HAPO anion exchange process to the reprocessing of Fast Ceramic Reactor (FCR) fuel using the Idaho Small Plant Concept. It is shown that the anion exchange flowsheet meets the reprocessing objectives of the FCR case and can be adequately accommodated in the Small Plant Concept. Capacities of up to 1550 Md(e) are feasible in the Small Plant and unit reprocessing costs range from 0.14 to 0.28 mills/kwh depending on the number of reactors to be processed. … more
Date: February 1, 1962
Creator: Alter, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1961

Description: Progress is reported on investigations in support of the Experimental Gas-Cooled Reactor, the Pebble-Bed Reactor Experiment, Advanced reactor design and development, test facilities, components, and materials. Topics covered include EGCR physics, EGCR performance analyses, structural investigations, EGCR component and materials development and testing, EGCR experimental facilities, PBRE physics and design studies, fueled-graphite investigations, clad fuel development, design studies of advanced… more
Date: February 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for Step Transient Loading Tests on the SM-1 : Task XII

Description: Abstract: This technical report evaluates hazards involved with SM- 1 plant response and system performance tests (Task XII), to determine the response of the SM-1 plant to step electrical and steam load changes. The report describes the changes in plant equipment and operating procedures for this task and evaluates these changes for possible additional hazards to those described in APAE No. 2, Revision 1, "Hazards Summary Report for the Army Package Power Reactor SM-1."
Date: February 1, 1962
Creator: Pomeroy, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HYDROLOGIC AND GEOLOGIC STUDIES FOR PROJECT GNOME. Preliminary Report

Description: Geologic lnformation required to define the pre- and post-shot physical and chemical characteristics of the sait and other rocks affected by the exploslon was gathered. Information on the pre- and post-shot hydrologic condltlons at the site and the surrounding area was also obtalned. (M.C.G.)
Date: February 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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[News Script: Arrest]

Description: Script from the WBAP-TV/NBC station in Fort Worth, Texas, covering a news story about police arresting jail escapee Ted Walters in West Dallas.
Date: February 1, 1962
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Script
Partner: UNT Libraries Special Collections
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[News Script: Assault trial]

Description: Script from the WBAP-TV/NBC station in Fort Worth, Texas, covering a news story about Jones Woody Bean of Garland being found not guilty of sexually assaulting a second-grader in Dallas.
Date: February 1, 1962
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Script
Partner: UNT Libraries Special Collections
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