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An assessment of the zirconium tube program -- C Reactor pilot demonstration installation

Description: Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.
Date: March 18, 1960
Creator: Amy, G. O.
Partner: UNT Libraries Government Documents Department
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THE BMI-16 RECIRCULATING GAS LOOP INSTALLED AT THE ETR

Description: A developmental program was conducted to provide and in-pile loop facility for use in evaluating gas-cooledreactor fuel asubassemblies. The program included the design, construction, and installation of a recirculating gas loop which is located in a 6 by 6-in. facility in the aluminum reflector of the ETR. The loop system was designed to recirculate the primary nitrogen coolant at flow rates up to 0.9 lb per sec and pressures up to 200 psia. It will accept fuel subassmeblies up to 36 in. in len… more
Date: March 18, 1960
Creator: Baum, J. V. & Francis, G. A.
Partner: UNT Libraries Government Documents Department
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Design of supplement B to PT-IP-262-A-11-FP, evaluation of projection fuel elements for use in ribbed process tubes

Description: One of the three major categories of HAPO fuel element failures is the side corrosion type rupture. The majority of side-corrosion failures has been characterized by oval or tear-drop shaped flow patterns containing evidence of accelerated corrosion. Thorough examination of many of these so-called `hot spot` failures has indicated the failure was caused by poor heat transfer associated with misalignment, dimensional distortion or poor jacket-to-core bonding. It has been postulated that misalign… more
Date: July 18, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Development of Thorium-Uranium-Base Fuel Alloys

Description: Thorium-uranium alloys were studied with the aim of developing alloys with improved irradiation behavior by control of microstructure. The effect of thorium purity, melting technique, hot and cold working, and heat treatment on microstructure was investigated. The most signifi- . cant microstructural differences occurred as a result of casting technique, The arc-melted alloys exhibited the most nearly ideal structure, that of a homogeneous dispersion of small-diameter uranium particles in a tho… more
Date: March 18, 1960
Creator: Farkas, Martin S.; Bauer, Arthur A. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department
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THE DIFFUSION OF RADIOACTIVE FISSION PRODUCTS FROM POROUS FUEL ELEMENTS

Description: The release of fission products from porous fuel elements during irradiation may be largely a diffusion process. An equivalent-sphere hypothesis was proposed to provide a model by which the diffusion can be analyzed. The equations of diffusion were previously solved for in- pile conditions. The slow convergence of the formulas makes the previous solutions awkward. In the present investigation alternate formulas were derived which are more suitable under certain circumstances. Tables were prepar… more
Date: April 18, 1960
Creator: Beck, S.D.
Partner: UNT Libraries Government Documents Department
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Effects of Irradiation on the Mechanical Properties of Tantalum

Description: Tensile, bend ductility, and hardness tests were performed at room temperature on irradiated tantalum sheet to determine the effect of irradiation on the strength and ductility. Sheet tensile specimens were irradiated in an attempt to produce corversions of tantalum to tungsten of approximately 1.5 and 3.0 wt.%. Unirradiated tantalum and arc-melted alloys of tantalum-1.5 and -3 wt.% tungsten were tested for comparison with the irradiated material. The tensile and yield strengths of tantalum wer… more
Date: November 18, 1960
Creator: Franklin, C. K.; Stahl, D.; Shober, F. R. & Dickerson, R. F.
Partner: UNT Libraries Government Documents Department
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Effluent system capacity Project CGI-883 increased process water flow -- 100-K

Description: The process water flow rates at the 100-K Reactors will be increased as a result of plant modifications under Project CGI-883. The flow rates to be achieved by the project are 188,000 and 200,000 gpm under five and six 190 Building pump operation respectively. Preliminary studies have indicated that the K-Area effluent systems will, for the most part, be adequate for the expanded conditions provided the reactor effluent is continuously and simultaneously discharged from two retention basis to t… more
Date: November 18, 1960
Creator: Schack, M. H.
Partner: UNT Libraries Government Documents Department
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Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis

Description: The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly the transient cases. The question… more
Date: April 18, 1960
Creator: Love, W. J.
Partner: UNT Libraries Government Documents Department
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Existing reactor rear face piping review

Description: The rear face or discharge area of a reactor contains all the appurtenances necessary to discharge irradiated fuel, to collect hot coolant from each process tube, to monitor tube and effluent temperatures, and to monitor the coolant for ruptured fuel elements. Generally, failure of a rear face piping component would not affect the safety of the reactor since the coolant has fulfilled its purpose, that of cooling the fuel elements. The failure may, however, cause failure of one of the monitoring… more
Date: May 18, 1960
Creator: Fox, J. M. Jr.; Harrison, C. W.; Reinig, L. P. & Watson, D. F.
Partner: UNT Libraries Government Documents Department
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Experimental Investigations of the Removal of Sodium Oxide From Liquid Sodium

Description: Experimental investigations were conducted to obtain additional information on the growth and characteristics of sodium oxide deposits in liquid sodium which could lead to system plugging. These investigations included the removal of sodium oxide from molten sodium by the cold trap method.
Date: January 18, 1960
Creator: Billuris, G.
Partner: UNT Libraries Government Documents Department
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Fuel Core Tester - UT-2

Description: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
Partner: UNT Libraries Government Documents Department
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Increased production study B, D, DR, F, H and C reactors

Description: This document studies a broad study program which is currently in progress in Irradiation Processing Department to evaluate the technical and economic feasibility of various methods of obtaining increased production from the six older reactors (B, D, DR, F, H, and C Reactors). Due to time limitations this study has been in general terms only, but has indicated that considerable increased plant return can be obtained from an increased conversion ratio as well as from higher reactor power levels.… more
Date: April 18, 1960
Creator: Fifer, N. F. & Kempf, F. J.
Partner: UNT Libraries Government Documents Department
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Military Field Expedient Shielding Experiment

Description: Convair-Fort Worth, under contract to the U.S. Army Engineer Research and Development Laboratories, performed experiments to obtain data for use in applying field materials to shield portable nuclear-reactor power plants.
Date: October 18, 1960
Creator: Wheeler, D. M. & Bostick, L. H.
Partner: UNT Libraries Government Documents Department
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MODIFIED ZIRFLEX PROCESS FOR DISSOLUTION OF 1-10% U-Zr ALLOY FUELS IN AQUEOUS NH$sub 4$F-NH$sub 4$NO$sub 3$-H$sub 2$O$sub 2$: LABORATORY DEVELOPMENT

Description: A modified Zirflex process was developed in the laboratory for dissolution of 1 to 10% uranium-zirconium alloy fuels to produce a nitrate solution from which uranium can be recovered by conventional solvent extraction methods. A flowsheet is presented for dissolution of 7% uraniumzirconium alloy in 5.4 M NH/sub 4/F-0.33 NH/sub 4/NO/sub 3/. Enough 1 M A/sub 2/O/sub 2/ is added continually during dissolution to yield 0.13 M H/sub 2/O/sub 2/ in the final solution, neglecting the amount reacting. D… more
Date: March 18, 1960
Creator: Gens, T.A.
Partner: UNT Libraries Government Documents Department
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Numerical results of production test IP-326-I, Low-flow calibration tests at B, D, F, and H Reactors

Description: Recent reviews of the last-ditch water backup system at the old reactors had shown that complete adequacy could not be demonstrated at all of the reactors under all conditions. However, these conclusions were based in part on conservative calculations using basic data with a sizeable amount of possible error. Subsequently, recommendations were made to run several tests which would increase the accuracy of the basic data and thereby allow an increase in the demonstratable level of last-ditch vat… more
Date: October 18, 1960
Creator: Benson, J. L.
Partner: UNT Libraries Government Documents Department
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Once Through Decontamination Studies- Interim Report No. 2

Description: The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This is the second interim report of a series that covers tests performed in the 242-B Single Pass Flow Facility. The first was distributed in January, 1960.
Date: February 18, 1960
Creator: Hokenson, J. F. & Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
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Partial modification of 190-KW pump No. 1, Project CGI-883: Increased process water flow, 100 K

Description: The 190-KW process water pumping Unit No. 1 is scheduled to be modified for increased pumping capacity under Project CGI-883- Component parts for this modification are expected to-be received during June 1960. Installation of these components would require approximately ten days; due mainly to grinding of the high lift pump case to make room for the new larger diameter impeller. In order to minimize lost production, it has been proposed by K Reactor Operation that the high lift pump be modified… more
Date: April 18, 1960
Creator: Schack, M. H.
Partner: UNT Libraries Government Documents Department
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A POTENTIOMETRIC STUDY OF ZIRCONIUM-NITRATE AND ZIRCONIUM-FLUORIDE SYSTEMS

Description: The potentiometric behavior of zirconium in fluoride, nitrate, and fluoride-nitrate systems is correlated and discussed in terms of the zirconium species present. A potentiometric titration was used successfully for the determination of total nitrate and zirconium in aqueous or organic (tributyl phosphate) zirconium-nitrate systems. (auth)
Date: August 18, 1960
Creator: Moffat, A. J.
Partner: UNT Libraries Government Documents Department
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