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Design and Construction of a Unit for Measuring Metal Skin Temperatures

Description: From summary: This report concerns the theoretical evaluation and experimental development of special thermocouples capable of being accurately located at or near the surface of metal structures to permit measurement of temperature distribution through the strictures.
Date: February 1961
Creator: Advanced Technology Laboratories
Partner: UNT Libraries Government Documents Department
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100-C water plant

Description: System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reactor use, 10,000 to 12,000 gpm was demanded by B Area through the 183 BC intertie. The maximum flow that the intertie line could handle, without reducing the filter capacity of the C Area filters, is about 21,000 gpm.
Date: February 20, 1961
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Description: Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the research and development program for the United States Atomic Energy Commission sodium Components Design Project.
Date: February 15, 1961
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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EBWR CORE 1A PHYSICS ANALYSIS

Description: The studies were primarily directed toward selection of the optimum loading for Core lA and a prediction of its properties. Included are analyses of some relevant experiments on Core 1, and prelimlnary modifications of Core 1 to Core lA. The factors which must be considered for the optimum loading determination are discussed. Four different loading pattenrs were investigated, which were considered to span the numerous possibilitles. Adequate cold shutdown was found to be almost unobtainable without the use of boric acid. For this reason, and because the heat transfer and stability limitations are severe, greater weight was given to heat transfer as opposed to control requirements. The use of boron-stainless steel poison strips fastened to the sides of the spike elements is considered insofar as in improving the loading from either the heat transfer or control standpoint. The relatlve advantages and disadvantages of the use of stainless steel fuel followers as opposed to Zircaloy followers are discussed. (B.O.G.)
Date: February 1, 1961
Creator: Avery, R.; Almenas, K.; Carson, C.; Iskenderian, H. & Kelber, C.
Partner: UNT Libraries Government Documents Department
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HRT CORROSION SAMPLES--ADDITIONAL DATA ON SPECIMENS REMOVED PRIOR TO RUN NO. 20

Description: Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined include core screen samples, core specimen array No. 1, blanket specimen array No. 2, core solution line specimen arrays No. 103 and 103A, and blanket solution line specimen array No. 203. These data include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. A summary is included of the HRT operating schedule during exposure of the specimens and of the status of examinations for the specimens removed from the reactor prior to run 20. (auth)
Date: February 1, 1961
Creator: Baker, J.E.; Silverman, M.D.; Jenks, G.H. & Olsen, A.R.
Partner: UNT Libraries Government Documents Department
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Revised requirements for continuous birch recovery at Redox

Description: The process criteria proposed use of the existing organic wash column, 10, as a stripping column for the neptunium accumulation and isolation cycles. It is now proposed to employ a new processing concept which will permit the use of the scrub section of the neptunium extraction column, 1S, for neptunium stripping thereby obviating the use of the 10 Column. This proposed new scheme will provide increased neptunium stripping efficiency and greater processing flexibility for the 1S Column. The revision will require four new jumpers, but will permit the deletion of eight jumpers required for the original proposal. This document discusses the technical bases and incentives for the proposed change and presents revised flow diagrams and jumper routings.
Date: February 2, 1961
Creator: Barnes, R. G.
Partner: UNT Libraries Government Documents Department
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A Spectrophotometric Atlas of the Spectrum of CH from 3000A to 5000A

Description: Report of the near ultraviolet and visible emission spectrum of CH presented in the form of a spectrophotometric atlas. The spectrum was recorded photoelectrically from an acetylene-oxygen flame in the region 4900 to 3000 A by use of a high-resolution grating monochromator. Each of the lines in the CH spectrum is identified.
Date: February 14, 1961
Creator: Bass, Arnold M. & Broida, H. P.
Partner: UNT Libraries Government Documents Department
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Specific activity of the NPR primary coolant loop

Description: In coolant system such as NPR's, the coolant activity level increase with each succeeding pass through the reactor flux until a saturation limit is reached. Therefore, the activity level of the NPR coolant system will be much higher than that of the old reactor once-through systems. This report is the determination of the specific activities (disintegrations/cc{center dot}sec) of the various coolant impurities which determine the total activity of the coolant system. 10 refs., 13 figs., 2 tabs.
Date: February 16, 1961
Creator: Bitz, D.A.
Partner: UNT Libraries Government Documents Department
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Interim goal exposure plans for O-III-NB and O-III-EB material for B, D, DR and F reactors

Description: The purpose of this report is to recommend variable goal plans for natural and enriched bumper fuel elements, specifically for 0-III-NB and 0-III-EB materials, to be irradiated at the B, D, DR, and F Reactors. The average goal exposure for all bumper fuel elements at D Reactor was specified to be 900 MWD/T, with provisions being made for revision by normal procedures. Exposures for enriched bumper material at the B, M. and F Reactors were not specified in the PITA supplement authorizing charging of this material.
Date: February 13, 1961
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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MUFT-5--A FAST NEUTRON SPECTRUM PROGRAM FOR THE PHILCO-2000

Description: The program was written for the Philco-2000 computer to provide a nuclear design computing tool equivalent to the IBM-704 computer program MUFT-4 and to provide a set of routines for a future spatial multigroup program, P/sub 3/ MG-1. In addition to the features of its 704 predecessor, MUFT-5 provides a more complete isotopic edit, an optional blackness coefficient edit, and the use of a complete P/sub i/->i>s library. The resultant program is found to be easier to use because of the simplicity of running several problems, more valuable because of the many additional results that are edited, and more economical because of the changes made in programming. (auth)
Date: February 1, 1961
Creator: Bohl, H. Jr. & Hemphill, A.P.
Partner: UNT Libraries Government Documents Department
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Engineering Applications of Analog Computers

Description: Six examples are given of the application of analog computers in the fields of reactor engineering, heat transfer, and dynamics: deceleration of a reactor control rod by dashpot, pressure variations through a packed bed, reactor kinetics over many decades with thermal feedback (simulation of a TREAT transient), vibrating system with two degrees of freedom, temperature distribution in a radiating fin, and temperature distribution in an irfinite slab with variable thermal properties. (D.L.C.)
Date: February 1, 1961
Creator: Bryant, L. T.; Janicke, M. J.; Just, L. C. & Winiecki, A. L.
Partner: UNT Libraries Government Documents Department
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A standard AlSi braze wetting test for aluminum components used in the lead-dip process

Description: Wetting of the aluminum components by aluminum-silicon brazing alloy is a major factor influencing the quality of the fuel elements. Several process variables associated with the impact extrusion of aluminum components influence the resulting Al surface. In addition, these processing variables interact with the HAPO component production cleaning process to give varying results. Purpose of this document is to define the parameters for selecting, preparing) testing and evaluating the AlSi wetting potential of aluminum components used in the lead-dip process, and to provide a tool for measuring the acceptability of aluminum components for the preparation of fuel elements.
Date: February 1, 1961
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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Feasibility Study of a New Mass Flow System. Period Covered January 1- January 31, 1961

Description: Machining was completed on the s-tube flow element, and a spring, for use at a constant known temperature, was constructed for the flow element. Calculations for geometry factor, detector efficiency, and effective absorption along the useful radiation path were completed for the reed densitometer. The flow rate control was calibrated and performed satisfactorily. Response to step transient changes occurred with a damping constant of about 0.6 and an effective response time of 10 sec. Sources of error in the s-tube flow rate measurements are discussed. (M.C.G.)
Date: February 15, 1961
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department
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A Condenser for the Vacuum Distillation of Metals

Description: A condenser, suitable for use in the distillation of metals was designed. The temperature of the condensing surface was established by controlling the pressure over boiling NaK-78 contained within the condenser. Performance was evaluated in test units in which pure bismuth was distilled as the test metal. (auth)
Date: February 1, 1961
Creator: Burnet, G. & Buchanan, W.
Partner: UNT Libraries Government Documents Department
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SELECTIVE REDUCTION OF PLUTONIUM(VI) TO PLUTONIUM(IV) IN A PLUTONIUM(IV-VI) NITRIC ACID SOLUTION

Description: The technique for adjusting the valence of Pu in the Pu(IV-VI) system to the Pa(IV) state for efficient solvent extraction or anion exchange is described. Investigations show that Pu(VI) may be reliably reduced to Pu(IV) with ferrous suifamate s. Nitric acid concentration must be between 2 and 6 M to avoid Pu disproportionation of suifamate precipitation. Ferrous sulfamate concentration is kept below 1 M to prevent crystal formation after the reaction, but Pu concentration may be as high as 250 g/l. (P.C.H.)
Date: February 1, 1961
Creator: Campbell, M.H.
Partner: UNT Libraries Government Documents Department
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Initial Peak Surge Current Detection Circuits

Description: Test requirements for several components specifies that surge currents be monitored to determine if the initial peak surge current exceeds a certain predetermined amplitude. This report describes and evaluates two circuits which were developed by Organization 2451 to meet this requirement in production testing.
Date: February 1961
Creator: Conrad, Milo M.
Partner: UNT Libraries Government Documents Department
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