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LOS ALAMOS POWER REACTOR EXPERIMENT NO. II, LAPRE II

Description: Design features and operating characteristies of the Los Alamos Power Reactor Experiment No. II are discusssd. Results of performance tests and of an examination conducted after disassembly of the reactor are presented. Recommendations for work on uranium phosphate fueled reactors are made. (auth)
Date: April 1, 1960
Creator: Clark, R.A. comp.
Partner: UNT Libraries Government Documents Department
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Automatic Dose Computer for Radiation Film Badges

Description: Technical report. From Abstract: "A combination densitometer and analog computer is described which determines radiation exposure of photographic film used in personnel badges. The range of the instrument is 0 to 300 mr gamma and 0 to 300 mrad beta plus gamma. A novel phototube circuit is used to obtain logarithms directly."
Date: April 1960
Creator: Davis, John E.
Partner: UNT Libraries Government Documents Department
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AUTOMATIC DOSE COMPUTER FOR RADIATION FILM BADGES

Description: A combination densitomer and analog computer is described which determines radiation exposure of photographic film used in personnel badges. The range of the instrument is 0to 300 mr gamma and 0 to 300 mrad BETA plus gamma . A novel phototube circuit is used to obtain logarithms directly. (auth)
Date: April 1, 1960
Creator: Davis, J.E.
Partner: UNT Libraries Government Documents Department
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CALCULATED REACTIVITY CHANGES PRODUCED BY THE OSCILLATION OF AN EPITHERMAL NEUTRON ABSORBER IN THE BULK SHIELDING REACTOR

Description: An attempt is made to ascertain the optimum working conditions of a pile oscillator and to compare this method with the danger coefficient technique from the point of view of minimum amount of resonance absorption which can be detected. The space-time behavior of the absorption properties of the sample is described by means of a delta -function and the reactor kinetic equations are obtained by using a single mode expansion of the flux. The results are applied to a bare reactor model equivalent to the fully reflected, parallelepiped BSR-I. (W.D.M.)
Date: April 1, 1960
Creator: Perez-Belles, R
Partner: UNT Libraries Government Documents Department
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Coextrusion of Powder-Compact Slugs

Description: Technical report. From Abstract: "A process was developed for manufacturing aluminum-clad slugs containing UO2 or ThO2 dispersed in an aluminum matrix. In this process a mixture of the oxide and aluminum powder is cold compacted to form the billet core, which is then coextruded with an aluminum sheath to produce the clad slug."
Date: April 1960
Creator: Marsh, Harold G.
Partner: UNT Libraries Government Documents Department
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A Confidence Limit Computer

Description: Introduction: Confidence limits as a mathematical tool are applicable to many development engineering and production engineering situations. In order to make confidence limits readily available to engineers, a computer was designed which will approximate certain confidence limits.
Date: April 1960
Creator: Muench, Joseph O.
Partner: UNT Libraries Government Documents Department
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A Confidence-Limit Computer

Description: A paper computer is presented for finding the fourth from three known variables: upper confidence limit, confidence level, number of observations, and number of events with a specified characteristic. Complete instructions for computer operation are given. (D.L.C.)
Date: April 1, 1960
Creator: Muench, Joseph O.
Partner: UNT Libraries Government Documents Department
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COOLANT FLOW DISTRIBUTION PERMEATION OF COOLANT THROUGH GRAPHITE

Description: An investigation was conducted to determine the effects of He leakage through EGCR moderator columns and fuel element sleeves on the core coolant flow distribution reported in study II-179-1. Results of the investigation are discussed and recommendations for design changes so that the total coolant bypass will remain the same as previously reported are made. (J.R.D.)
Date: April 1, 1960
Creator: Kintner, L.L.
Partner: UNT Libraries Government Documents Department
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Design study interim report, RMA button line radiation reduction

Description: The design approach followed in this study is that of handling and processing plutonium solution and powders within tightly sealed but readily replaceable units of processing equipment, each one of which will do one step in the overall process. The presently used method is to use open equipment enclosed in glove boxes attached to a transporting device. Elimination of the glove box enclose and its replacement by tightly sealed and detachable equipment provides the accessability necessary for equipment repair and reduction of down time, thereby reducing costs. Most of the primary functions for the entire button line have been studied and no insurmountable design problems have been encountered. Studies of the pre-reduction and filtrate treatment functions and the PR can unloading and RC can loading equipment have been summed up and compiled into a design criteria. Design concepts for all of the equipment for processing from the nitrate through the button stage have been worked out and appear to be acceptable approaches, except for the vacuum drum filter and the vibrating tube reactor. The latter two components have been studied and drawings prepared; however, the concepts developed are not considered entirely acceptable from the operation and maintenance standpoint. Because of these shortcomings, alternative approaches are being considered for both components. Present plans call for investigation of a newly developed 6-inch continuous centrifuge to replace the vacuum drum filter, and a ribbon screw-type reactor to replace the vibrating tube. Both substitutions are to be verified by a testing program.
Date: April 1, 1960
Creator: Kolb, J. W. & Bellarts, H. J.
Partner: UNT Libraries Government Documents Department
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DESIRABILITY OF CHEMICAL DECLADDING FROM THE WASTE DISPOSAL VIEWPOINT

Description: Chemical decladding of stainless-steel- and Zircaloyjacketed fuel elements is discussed relative to cladding activation and waste-disposal cost as compared with a total dissolution process. (C.J.G.)
Date: April 1, 1960
Creator: Irvine, A R
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT AND PRODUCTION OF URANIUM 10 wt.% MOLYBDENUM AS-CAST SLUGS FOR HNPF PHYSICS EXPERIMENT

Description: A multiple casting process was developed for the production of 0.590 plus or minus 0.005-in. diam. by 12-in. long solid right cylinders. The process involves vacuum induction melting in MgZrO/sub 3/ coated graphite crucibles and casting into coated graphite molds. Thirty-eight hundred fifty 90 wt.% U of 1.5 wt.% enrichment-10 wt.% Mo as-cast pins were produced for HNPF Exponential Experiments. (auth)
Date: April 1, 1960
Creator: Stanley, J.A. & Binstock, M.H.
Partner: UNT Libraries Government Documents Department
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The Effects of Reactor Irradiation on the Thermoelectric Properties of Lead and Bismuth Tellurides

Description: Commercially available specimens of polycrystalline nand p-type lead telluride and n- and p-type bismuth telluride were irradiated in the Engineering Test Reactor. Total integrated flux times of 1.5 x 10/sup 20/ neutrons/cm/sup 2/ (thermal) and 1.6 x 10/sup 19/ neutrons/cm/sup 2/ (fast, i.e., for neutrons having energies greater than 1 (Mev) were accumulated by the specimens during irradiation. The specimen temperature during irradiation was 60 plus or minus 20 deg C. The effects of the irradiation on the thermoelectrical properties of these materials were found to be due almost entirely to fast neutrons insofar as most of the damage is healed during heat treatment. Increases in the electrical resistivity for irradiated n type PbTe and Bi/sub 2/Te/sub 3/ were found to anneal at temperatures below 200 deg C. Measurements of the electrical resistivity and Seebeck coefficient as a function of temperature for irradiated and unirradiated samples cut from the same ingot are given for all materials except p type PbTe. For the latter sample only the measurements of the Seebeck coefficient are given. (auth)
Date: April 1, 1960
Creator: Corelli, J. C. & Frost, R. T.
Partner: UNT Libraries Government Documents Department
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END-LOSSES FROM MIRROR MACHINES

Description: A theoretical treatment of the loss of plasmas from the ends of magnetic mirror machines, based on the FokkerPlanck equation is given. The plasma losses are described in terms of the evolution in time of distribution functions. Some supplementary calculations based on these distribution functions were made. These include charge-exchangereaction rates and fusion-reaction rates for the DD and DT reactions. (auth)
Date: April 1, 1960
Creator: Roberts, J.E. & Carr, M.L.
Partner: UNT Libraries Government Documents Department
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Evaluation of Irradiated Experimental OMR Fuel Elements--1

Description: As part of a program to develop an economical fuel cycle for an Organic Moderated Reactor (OMR), experimental fuel elements are being irradiated in the Organic Moderated Reactor Experiment (OMRE). The first two experimental fuel elements have been removed from the OMRE, examined, and evaluated. These extended-surface, platetype fuel elements had finned aluminum cladding, metallurgically bonded to flat uranium alloy fuel plates. A 0.0005 in. nickel layer was used to prevent interdiffusion between the aluminum and uranium. The fuel core alloys irradiated were U--5.5% Mo and U--3.5% Mo--0.5% Si. These two experimental elements were removed from the reactor after one of the elements released fission products, and cladding temperatures increased on both fuel elements. The maximum measured cladding temperature was 780 deg F. The maximum fuel burnup was later determined to be 0.25 at.% U. Hot-cell examination revealed that the coolant inlet ends of the fuel elements had filtered particulate matter out of the coolant, which blocked the ends of the coolant channels. Restriction of the coolant flow through the elements caused partial melting of the cladding in one fuel element and a blister on one of the fuel plates from the other fuel element. Dimensions were taken on three of the fuel plates. Metallographic sections from the blistered fuel plates were examined, and burnup profiles were determined for the three plates measured. The fuel had good dimensional stability, which is significant, since the melted cladding and the core microstructure evidenced temperatures substantially above the maximurn temperatures recorded by thermocouples. Nothing was observed that would indicate the fuel elements would not have functioned properly in the same coolant if the coolant were free of particulate matter of sizes that could be trapped. (auth)
Date: April 1, 1960
Creator: Walter, J. H.; Garrett, E. E. & Davis, J. M.
Partner: UNT Libraries Government Documents Department
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Evaluation of Plated-Through Connections for Printed Circuit Boards

Description: The present report describes the evaluations conducted with plated-through connections produced by techniques used by some of the prominent fabricators of printed circuits.
Date: April 1960
Creator: Voida, George & Eich, Norbert J.
Partner: UNT Libraries Government Documents Department
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Evaluation of Plated-Through Connections for Printed Circuit Boards

Description: Concepts of metallizing dielectric surfaces by copper re duction or immersion deposition are discussed. Step-bystep processing techniques for producing quality platedthrough connections are described. A description of the tests performed on the plated-through connections is given (C.J.G.)
Date: April 1, 1960
Creator: Voida, G. & Eich, N.J.
Partner: UNT Libraries Government Documents Department
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Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1959 - March 1, 1960

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: April 1, 1960
Creator: Hardy, Edward P., Jr. & Klein, Stanley
Partner: UNT Libraries Government Documents Department
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HEAVY WATER MODERATED POWER REACTORS. Progress Report for February 1960

Description: At the end of February 1960, 30% of the construction of the Heavy Water Components Test Reactor (HWCTR) was compplete. Limits for safe operation of the reactor were defined, and the general procedures for startup, shutdown, and normal operation here formulated. A detailed analysis of operating stresses in the reactor vessel defined the ling that can be tolerated. Core swelling produced a maximum cladding strain of 0.7% in a Zircaloy-2-clad tube of U-2 wt.% Zr that was irradiated to an average burnup of 1100 Mwd/t in the VBWR. (For preceding period see DP-465.) (auth)
Date: April 1, 1960
Creator: Hood, R.R. & Isakoff, L. comp.
Partner: UNT Libraries Government Documents Department
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HEAVY WATER MODERATED POWER REACTORS. Progress Report for March 1960

Description: Safeguards analyses of the boiling D/sub 2/O loop of the Heavy Water Components Test Reactor (HWCTR) show that neither a power failure nor a loss of cooling water will cause a serious accident if the reactor is scrammed. Construction was started on a full-scale mockup of the bayonet for this loop. The mockup will be used for studies of possible vibration phenomena associated with the flow of steamwater mixtures. Emphasis in the development of uranium metal fuel for power reactor use has been shifted to coex truded tubes that have a higher surfacs-to-volume ratio than those fabricated heretofore. The modified tubs design will permit higher powers to be achieved without exceeding thermal limitations, end offers the potential advantage of improved metullurgical behavior during irradiation. A swaged tube of uranium oxide with stailness steel cladding apparently failed during irradiation. (auth)
Date: April 1, 1960
Creator: Hood, R.R. comp.
Partner: UNT Libraries Government Documents Department
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