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Purification of mercury contaminated lithium hydroxide

Description: The object of this investigation was to determine an economical method of preparing pure lithium hydroxide from a mercury-contaminated lithium hydroxide monohydrate salt presently produced as a waste product. Pure lithium hydroxide has application for chemical removal of carbon dioxide from air and general open market sale if the mercury contamination is reduced to approximately one part per billion. Because of the uncertainty of the form of the mercury contaminant, different purification metho… more
Date: October 18, 1960
Creator: Bronfin, B. R.; Jenkins, D. M. & Wright, E. E. Jr.
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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Proposal to include blanket loadings in our plant improvement program

Description: Test metal was irradiated to simulate a `blanket` loading and striped E-N load under PT-IP-255-A-9-FP. The product analysis has now been obtained on the test material. The interpretation of this data and plant direction that might follow is considered in this document.
Date: November 18, 1960
Creator: Lang, L. W.
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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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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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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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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Quarterly Health Physics Report Through December 31, 1959 (Deleted Version)

Description: A resume of Health Physics activities for October, November, and December, 1959 is presented. Discussions and tabulations which summarize results of field surveys, bioassay, personnel monitoring, and environmental serveys are included.
Date: February 18, 1960
Creator: Meyer, H.E.
Partner: UNT Libraries Government Documents Department
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STUDY OF THE BETA TREATMENT OF URANIM. Progress Report to the Oak Ridge Operations Office for the Period November 1, 1959-April 1, 1960

Description: Activities in a program to determine the effects of product size (or dimensions), composition, and heat treatment on beta-treated U are reported. Progress to date was chiefly confined to organizing the program and setting up equipment. A Jominy end-quench apparatus was constructed, and preliminary experiments were run on as-cast metal to test the Jominy-oscillographthermocouple system. Results are tabulated. The method to be used for characterization of beta-treated samples by determination of … more
Date: April 18, 1960
Creator: Russell, R.B.
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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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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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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SAFEGUARD REPORT ON THE PROPOSED METHOD OF ANNEALING GRAPHITE IN THE X-10 REACTOR

Description: gone approximately 16 years of almost continuous irradiation. Throughout this time stored energy has accumulated at a slow rate to the present maximum value of about 35 cal/gm releasable to 250 deg C. A small portion of the moderator (approximately 4%) contains stored energy which under adiabatic conditions may be released spontaneously (at approximately 165 deg C) to produce a maximum temperature of 270 deg C. Careful analysis has shown that the presert condition is not hazardous; however, it … more
Date: May 18, 1960
Creator: Stanford, L.E.; Wittels, M.C.; Ramsey, M.E. & Cagle, C.D.
Partner: UNT Libraries Government Documents Department
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River Soundings. Core I, Seed 2. Test Results

Description: Water depth in the intake channel to the coolant-water screenhouse and surrounding area in the Ohio River near the intake channel were measured. From these measurements, the amount of silt removed during a previous dredging was determined. (C.J.G.)
Date: July 18, 1960
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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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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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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