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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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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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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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Solids Separation by a Hydraulic Cyclone With a Batch Underflow Receiver

Description: >Engineering correlations based on experimental studies are presented for the application of batch accumulation of solids separated from solid-liquid feed to a cyclone. This method of cyclone operation simplifies the problem of flow control involved with continuous underflow. The efficiency and capacity correlations for hydroclones with continuous underflow also apply to this type of operation. The volume flow exchanged with the underflow receiver may be varied from 0.2 to 6% of the feed flo… more
Date: March 18, 1960
Creator: Haas, P. A.
Partner: UNT Libraries Government Documents Department
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Thermal Stresses In A Liquid Hydrogen Transfer Line

Description: A variable-length vacuum-insulated liquid hydrogen transfer line is described. The vacuum system is semi-permanent, and segments of the line are assembled with only threaded vacuum fittings. Thermal stress calculations are presented for a statically indeterminate union coupling.
Date: March 20, 1960
Creator: Pope, William L.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for February 1960

Description: Production Pu nitrate and unfabricated Pu metal during Feb. was below forecast; however FY output is above forecast. Production of UO{sub 3} exceeded commitments; shipments met schedule. Decontamination performance of Purex solvent extraction system was subnormal. Pu nitrate solutions were concentrated. A fire occurred in Purex N Cell during conversion of ion exchange prototype to production facility.
Date: March 21, 1960
Partner: UNT Libraries Government Documents Department
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Conductive Flooring for Hospital Operating Rooms

Description: Report issued by the Bureau of Standards over studies on the importance of conductive flooring in hospitals. Types of conductive flooring are compared, and tested. The methods and results are presented, and discussed. This report includes tables, illustrations, and photographs.
Date: March 21, 1960
Creator: Boone, Thomas H.; Hermach, Francis L.; MacArthur, Edgar H. & McAuliff, Rita C.
Partner: UNT Libraries Government Documents Department
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Effects of the Maximum Credible Accident Relevant to the Design of the Containment Shell, Experimental Low-Temperature Process Heat Reactor Project

Description: The effects of the maximum credible accident relative to the design of the containment shell are discussed. The maximum credible accident is defined. The thermal and hydraulic effects of the maximum credible accident on the reactor system were analyzed. The extent to which fuelrod cladding will melt was estimated. The amount of energy released from the reactor system by the escaping steam and water and by a possible chemical reaction was calculated along with the corresponding pressure rise ins… more
Date: March 21, 1960
Partner: UNT Libraries Government Documents Department
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Numerical Three Dimensional Temperature Analysis of the EGCR Fuel Rod

Description: The temperature field in an outer rod of the Experimental Gas Cooled Reactor fuel assembly is presented. The numerical analysis has taken account of the three dimenhas considered the four resons involved. that is. fuel pellets, ceramic disc, steel end caps. and cladding. The convective heat transfer coefficient and fluid temperature were considered constant over the 2.185 in. of rod length studied. (auth)
Date: March 21, 1960
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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The Pilot Plant Operation of a Vertical Tube, Recirculating Dissolver for the Dissolution of Uranium Dioxide in Nitric Acid

Description: The need for criticality control in the proposed reprocessing of slightly enriched non-production fuels at Hanford has led to the development of a geometrically "safe", vertical tube, recirculating dissolver. A study of the nitric acid dissolution of uranium dioxide in a pilot plant dissolver of this type is reported here. The study was pointed toward the comparison of uranium dioxide dissolution rates in a batch and a recirculating dissolver and the definition of hydraulic problems associated … more
Date: March 21, 1960
Creator: Smith, P. W.
Partner: UNT Libraries Government Documents Department
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Status report - C Reactor process tubes

Description: Data have recently been obtained on a number of C-Reactor process tubes. These data make is possible to reassess the current conditions of the tubes in the C-Reactor and hence to re-evaluate the probable data when retubing of the reactor will have to be started. The results of this reassessment are presented below.
Date: March 21, 1960
Creator: Miller, N. R.
Partner: UNT Libraries Government Documents Department
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Density and Hydrogen Content of Uranium Oxide Cakes and Slurries

Description: The work described was undertaken to provide data for nuclear safety studies concerning NPF reprocessing equipment. The original objective was to determine the uranium density and water (hydrogen) content of UO2-H2O mixtures ranging from compact centrifuge cakes to dilute slurries. The scope was later expanded to include mixtures of UO2 with hydrocarbon oil and mixtures of UO3-H2O.
Date: March 22, 1960
Creator: Amos, L. C.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department, monthly record report, February, 1960

Description: This document details activities of the irradiation processing department at the Hanford Reservation during the month of February, 1960. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operation; Manufacturing Operation; Facilities Engineering Operation; Relations Practices Operation; Financial Operation; and NPR operation.
Date: March 22, 1960
Partner: UNT Libraries Government Documents Department
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DESIGN STUDIES ON CESIUM-137 AS A SOURCE FOR HIGH LEVEL GAMMA IRRADIATORS. Quarterly Progress Report No. 3 Covering the Period from December 1, 1959 to March 1, 1960

Description: Experiments were carried out on a Cs/sup 137/ plaque source of 40 x 40 x 1/2 inches. Measurements were made of dose distributions in water and of photon spectral distributions in paraffin. For 9-inch-thick water siab absorbers without air gaps, it was found from the preliminary experiments that the depth dose uniformity can be varied over the range 1.10 to 1.40. The absolute dose rates found were in general agreement with design predictions which indicate irradiator efficiencies in the region o… more
Date: March 23, 1960
Creator: Voyvodie, L.
Partner: UNT Libraries Government Documents Department
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A Mathematical and Statistical Approach to the Design and Analysis of a Reactor Containment Vessel Pressure Test

Description: This report discusses the mathematical and statistical questions concerned with the estimation of a leak rate from data collected during a reactor containment vessel pressure test such as that performed on the PRTR vessel in May, 1959. A mathematical method is suggested in Section 3 for the construction of a total number of gas molecules in the containment vessel time series using vessel absolute pressure and temperature readings at several positions within the vessel. A formula for the precisi… more
Date: March 23, 1960
Creator: Nicholson, W. L.
Partner: UNT Libraries Government Documents Department
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Radioactive Fallout From Nuclear Explosions

Description: A nontechnical description of the mechanisms of local and world-wide fall-out from nuclear explosions is given. The relative importance of local fall-out in a nuclear war is discussed. The effects upon man of world-wide fall-out from past nuclear testing is discussed. It is pointed out that doses to man frcm testing are quite small when compared to the natural radiation background. (auth)
Date: March 23, 1960
Creator: Parker, E.N.
Partner: UNT Libraries Government Documents Department
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Scope report Safety Circuit Trip Identification System

Description: The purpose of this report is to establish the scope of a project to provide a system which will quickly and accurately identify the sources of all reactor scrams.
Date: March 23, 1960
Creator: Deichman, J. L.
Partner: UNT Libraries Government Documents Department
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SM-2 Clutch Testing

Description: The criteria and methods for test evaluation of electromagnetic clutch characteristics are discussed. An evaluation of the relative merits of two commercial clutches, both of the multiple disk friction type, is presented with test results. One of these clutches was incorporated in the clutch assembly design for the Array Reactor (SM-2). (auth)
Date: March 23, 1960
Creator: Hauenstein, G. C.
Partner: UNT Libraries Government Documents Department
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Volatilization of Cesium During Calcination and Hydrolysis of Cs2ZnFe(CN)6 Precipitates

Description: The feasibility of removing and recovering cesium-137 from various HAPO process solutions by precipitation of Cs2ZnFe(CN)6 has been demonstrated previously. Pilot plant studies of calcination and steam hydrolysis of non-radioactive Cs2ZnFe(CN)6 precipitates by members of the Process Equipment Development Operation are currently in progress. In support of these pilot plant studies, experiments were performed to determine the extent, if any, to which cesium volatilizes during calcination and hydr… more
Date: March 23, 1960
Creator: Bouse, Donald G. & Schulz, Wallace W.
Partner: UNT Libraries Government Documents Department
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Alpha correlation

Description: This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.
Date: March 24, 1960
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
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Hydraulic demand curves for standard BDF geometry at low tube powers

Description: Information concerning the pressure-flow relations in reactor process tubes at very low heat generation rates is of value for determining flow requirements during shutdown conditions. Since such information is quite difficult to calculate when boiling occurs, a brief laboratory investigation was conducted to obtain experimental data. The data obtained for BDF geometry are recorded in this report for distribution to those persons having an interest in the application of the results to reactor op… more
Date: March 24, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
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