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Alpha Air Monitoring with [alpha]/[beta] Ratio Compensation for Natural Interference

Description: Abstract. Results are presented of a theoretical study to calculate the [alpha]/[beta] ratio of filter-collected natural airborne radioactivity. The detection of airborne plutonium contamination by noting increases in this [alpha]/[beta] ratio is discussed. A modification of this approach which provides a more uniform response to alpha airborne contamination is described.
Date: February 5, 1962
Creator: Lindeken, C. L. & Montan, Donald N.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Analysis of Carbon Monoxide-Nitrogen Mixtures by High Resolution Mass Spectrometry

Description: From abstract: "A single focusing mass spectrometer has been converted into a double focusing instrument. Relatively high resolution is obtained by decreasing the slit widths and minimizing the ion-optic aberrations. A relatively low ion accelerating voltage (2000 volts) is utilized compared to those normally used for high resolution work. The entire construction was performed at these laboratories. Essentially all of the original equipment was reused in the double focusing system. Although the… more
Date: February 1962
Creator: Conzemius, Robert Joseph & Svec, Harry J. (Harry John), 1918-
Partner: UNT Libraries Government Documents Department
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Army Reactors Program Progress Report

Description: Research and development on metallurglcal aspects of pressurized-water systems is summarized. A survey was made of the methods of determining fuel burnup. The mechanisms and kinetics of the loss of boron during heating at 1135 deg C in various dynamic environments were determined. A model was developed to quantitatively characterize the UO/sup 2/ dispersion microstructure of roll-clad fuel plates relative to an ideal'' dispersion. In order to avoid the loss of boron from UO//sub 2/- stainless s… more
Date: February 14, 1962
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.
Partner: UNT Libraries Government Documents Department
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BWR Reference Design for PL-3

Description: Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant eq… more
Date: February 28, 1962
Creator: Humphries, G. E.
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.
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.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: January 1962

Description: This report, for January 1962 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: February 21, 1962
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for October-December 1961

Description: Recovery of Th (and U) from Granitic Rock. Recovery of Th by acid leaching ten addltlonal granite samples (36 to 82 ppm Th) from the Conway formation in N. H. ranged from about 50 to 85%, and averaged about 70%, Study of the effect of grind size on the recovery of Th from Conway and Plkes Peak granites showed no significant differences in the range minus 20 to minus 200 mesh. The Th concentration in a sized Conway granite sample was found to be much greater in the fine than in the coarse fracti… more
Date: February 21, 1962
Creator: Brown, K.B.
Partner: UNT Libraries Government Documents Department
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THE CHEMISTRY OF NIOBIUM IN PROCESSING OF NUCLEAR FUELS

Description: The chemical and industrial literature and laboratory work concerned with processing of niobium-containing nuclear fuels are reviewed. 57 references. (auth)
Date: February 1, 1962
Creator: Gens, T.A.
Partner: UNT Libraries Government Documents Department
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Chemonuclear Processing

Description: Technical report giving an overview of the use of nuclear energy to produce chemicals including a rough estimate of the economic potential.
Date: February 1962
Creator: Steinberg, Meyer, 1924-
Partner: UNT Libraries Government Documents Department
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Comparison of Gaseous Waste Handling Systems for PL-3

Description: Gaseous waste handling systems are compared for direct and indirect boiling water and pressurized water reactors for PL-3 application. Areas that are common to the various concepts are not discussed since they do not enter into a comparison study. The major differences present are in the handling of active gases released to or held in the primary system coolant. These gases which could be present, their possibIe release from the system, and the necessary processing requirements are discussed in… more
Date: February 28, 1962
Creator: Noble, J. H. & Duke, E. E.
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
Partner: UNT Libraries Government Documents Department
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Conceptual Design for 75 MWe Mixed Spectrum Superheating Reactor Power Plant

Description: "This report presents the conceptual design of a 75 MWe prototype Mixed Spectrum Superheater power plant. The scope of the work has emphasized primarily the design, performance, and cost information on the nuclear portion of the plant. The research and development programs required to insure plant feasibility are also present."--Intro.
Date: February 25, 1962
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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Conceptual Design for a 75 MWE Mixed Spectrum Superheating Reactor Power Plant

Description: The design, performance, and cost information on the nuclear portion of the Mixed Spectrum Superheater power plant are emphasized. The research and development programs required to ensure plant feasibility are also presented. The nuclear steam supply system, reactor auxiliary systems, radiation control systems, control and instrumentation, special test instrumentation, plant operation and maintenance, steam cycle, turbine plant, general service systems, preliminary safeguards considerations, ex… more
Date: February 25, 1962
Creator: Brynsvold, G. V.; Hikido, K.; Reynolds, A. B. & Riley, D. R.
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.
Partner: UNT Libraries Government Documents Department
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CRITICALITY EXCURSION OF NOVEMBER 10, 1961

Description: A criticality excursion occurred at the Oak Ridge Critical Experiments Laboratory on November l0, l961 as enriched uranium metal, neutron reflected and moderated by hydrogen, was being assembled. It is estimated that the energy yield was between 10/sup 15/ and 10/sup 16/ fissions. There was no personnel exposure or property damage. Fission product contamination, both airborne and contained in the metal, decayed sufficiently overnight to allow unhindered continuation of the experiment. The excur… more
Date: February 13, 1962
Creator: Callihan, D.
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
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
Partner: UNT Libraries Government Documents Department
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