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WELDING AND BRAZING OF HIGH-TEMPERATURE RADIATORS AND HEAT EXCHANGERS

Description: Procedures were developed for fabricating highperformance radiators and heat exchangers for the Aircraft Nuclear Propulsion (ANP) Program. These components, which contain multitudes of tube-to-tube sheet and tube-to-fin joints, are similar in design to those under consideration for a variety of space vehicle applications. In order to ensure reliability of the tube-to-tube sheet joints, techniques producing welds of extremely high quality were used and back brazing of the welds with a suitable a… more
Date: February 20, 1962
Creator: Slaughter, G.M. & Patriarca, P.
Partner: UNT Libraries Government Documents Department
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Administration of ORNL Research Reactors

Description: Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)
Date: August 20, 1962
Creator: Casto, W. R.
Partner: UNT Libraries Government Documents Department
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REPORT ON GLOVE BOXES AND CONTAINMENT ENCLOSURES

Description: Criteria and guide lines are presented for the design, construction, and operation of safe, economical, and efficient glove boxes and associated facilities based upon present conditions and anticipated changes. Comprehensive discussion of glove box materials and components, safety and fire prevention methods, health physics problems, operational considerations, and brief descriptions of AEC installations are included. (39 references) (C.H.)
Date: June 20, 1962
Creator: Garden, N.B. ed.
Partner: UNT Libraries Government Documents Department
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MTR Fast Neutron Flux Measurements for Cycle 146

Description: The fast neutron fluxes in selected positions of the MTR were measured for Cycle 146. The measurements were made at the beginning, throughout, and at the end of the cycle (564 Mwd). Vertical traverses for each position monitors are shown. (auth)
Date: March 20, 1962
Creator: Weber, L. D. & Hogg, C. H.
Partner: UNT Libraries Government Documents Department
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CHARACTERIZATION OF UO$sub 2$ POWDERS. Fourth Quarterly Report, July 10, 1961-October 10, 1961

Description: Studies are described of UO/sub 2/ powders to determine the relation between properties of the powders and sinterability. The main effort during the period was devoted to correlation of the powder particle size distribution with the sintered density of pellets. The pressure applied during the green forming step of pellet production is shown to have a varied and considerable effect on ceramic particle size distribution in the pellets. (J.R.D.)
Date: January 20, 1962
Creator: Carpenter, J.F.; Kuhlman, C.W. & Nelson, R.A.
Partner: UNT Libraries Government Documents Department
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GENERAL STANDARDS GUIDE FOR EXPERIMENTS IN ORNL RESEARCH REACTORS

Description: The Oak Ridge National Laboratory has three generalpurpose research reactors which accommodate testing loops, target irradiations, and beam-type experiments. Since the experiments must share common or similar facilities and utilities, be designed and fabricated by the same groups, and meet the safe safety criteria, certain standards for these have been developed. These standards deal only with those properties from which safety and economy of time and money can be maximized and do not relate to… more
Date: August 20, 1962
Creator: Cagle, C.D.
Partner: UNT Libraries Government Documents Department
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Pilot Plant Development Studies of a Continuous Process for Recovering Uranium From Nichrome Fuels

Description: Pilot plant studies were conducted to develop a continuous process for recovering uranium from nichrome fuels (HTRE). The process consisted of dissolution of fuel in mixed HCl--HNO/sub 3/ solution, removal of the chloride ion by stripping with HNO/sub 3/ in a packed column, and then recovery of the uranium by TBP solvent extraction. Recovery of uranium from nichrome fuels at satisfactory rates and efficiencies can be obtained by this process. Reactor fuels containing large amounts of silica may… more
Date: June 20, 1962
Creator: Chamberlain, H. V.
Partner: UNT Libraries Government Documents Department
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Strontium, Strontium-90, and Calcium Analyses of Clinch and Tennessee River Clams

Description: Analyses of clam shells for Sr, Sr/sup 90/, and Ca are reported. The data include 208 Sr, 80 Sr/sup 90/, and 35 Ca analyses. Information on age of the clam and shell weight are also included because the Sr concentration in some shells is affected by age and growth rate. A detailed description of sample treatment and preparation is also included. (auth)
Date: June 20, 1962
Creator: Nelson, D. J.
Partner: UNT Libraries Government Documents Department
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Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Pilot Plant Calciner. Part I. Equipment Development and Initial Process Studies

Description: A two-foot-square fluidized bed calciner was designed and operated to convert aqueous, highly radioactive wastes into granular solids. The calciner exceeded its designed feed capacity of calcining, at a bed temperature of 400/sup 0/C, 100 liters per hour of aluminum nitrate solution simulating wastes from the reprocessing of spent aluminum-uranium alloy reactor fuel. Heat was supplied to the calciner by circulating NaK with an electromagnetic pump, at temperatures up to 1400/sup 0/F, through a … more
Date: June 20, 1962
Creator: Brown, B. P.; Grimmett, E. S. & Buckham, J. A.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: July 1962

Description: This report, for July 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; and safety and security.
Date: August 20, 1962
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: March 1962

Description: This report, for March 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: April 20, 1962
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Development test No. IP-558-T Gas Sampling Facility correlated with front to rear thermocouple stringer: KW Reactor

Description: The test detailed in this report authorizes the installation of sampling tubes in the vacant-positions in one of the two front-to-rear graphite stringers to be installed in KW Reactor in January 1963. These lines will permit withdrawal of a gas sample from the active zone at a point where the graphite temperature is being measured. Analysis of this gas sample on the gas chromatograph and on a new catalytic oxygen-hydrogen instrument is expected to yield valuable information on graphite burnout … more
Date: December 20, 1962
Creator: Cooke, J. P. & Baars, R. E.
Partner: UNT Libraries Government Documents Department
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Numerical results of PT IP-412-AI, B and C reactors export system test

Description: The purpose of this document is to present the numerical results of a production test of the last ditch water backup system performed at B and C reactors on December 15, 1961. The main purpose of the production test was to determine more accurately the capacity of the export system for supplying flow to a dual reactor area under several simulated emergency conditions where BPA power to all areas has been interrupted and the steam supply to one old area has been lost. In addition, the flow capac… more
Date: February 20, 1962
Creator: Benson, J. L.
Partner: UNT Libraries Government Documents Department
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Flow tests of C reactor outlet elbow replacement fittings

Description: A new outlet elbow fitting has been designed for use on C reactor to replace those elbows which fail because of stripped threads where the elbow connects to the rear nozzle barrel. There are two models of this threadless elbow, one providing for a water thermocouple only, and one providing for a thermocouple and an RTD. Flow tests have been conducted to determine the pressure drop across these outlets and the pressure drop has been compared to the pressure drop across the previously used outlet… more
Date: July 20, 1962
Creator: Waters, E. D.
Partner: UNT Libraries Government Documents Department
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KER-3 operating report test K-3-16, PT IP-477-A

Description: The objective of this production test was to evaluate the irradiation behavior of N. Reactor fuel elements at conditions equivalent to or more severe than those expected in N Reactor. The thermocouple train consisted of eleven 23-inch NAE1 elements (replicas of an N Reactor fuel element) plus five 16-inch tubular perfs. The elements were enriched to 0.947 per cent. They were coextruded Zircaloy-2 jacketed self-supported uranium tubes concentrically nested one within the other to provide an elem… more
Date: November 20, 1962
Creator: Quinn, H. T.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: June 1962

Description: This report, for June 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; and safety and security.
Date: July 20, 1962
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
open access

SNAPSHOT Safety Program Plan

Description: The SNAPSHOT Safety Program, as described in this document, is therefore formulated to align safety studies performed by separate agencies and their contractors. At the present stage in program development, the plan is principally concerned with the initial SNAPSHOT flight (SNAP 10A). SNAPSHOT represents a special flight mode for the initial reactors operated in space. The flights are designed to permit early space reactor tests prior to resolving all the safety proglems that may be associated … more
Date: June 20, 1962
Partner: UNT Libraries Government Documents Department
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PREDICTION OF THE CRITICAL HEAT FLUX IN FORCED CONVECTION FLOW

Description: A superposition model is developed to predict the critical heat flux in forced convection flow. The model is applied to available experimental results in boiling water flows and good agreement is obtained between the model and test data over the multitude of geometries, flow rates, pressures, and fluid enthalpies tested to date. (auth)
Date: June 20, 1962
Creator: Levy, S.
Partner: UNT Libraries Government Documents Department
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Friction binding of sliding parts

Description: No Description Available.
Date: November 20, 1962
Creator: Igne, E.G.
Partner: UNT Libraries Government Documents Department
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