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ORR Operations for Period April 1961 to April 1962

Description: A summary of the activities in the 4th operational year is presented for the ORR. On-stream time at 30 Mw was relatively steady with 75.4 and 83.7% representing the lowest and highest quarters. Modification of the ball-latch mechanism of the shim-rod-drives is in progress. The primary cooling system bypass control valve was modified and a d-c pony motor was added at the No. 3 primary pump. This addition was made to increase the reliability of adequate water flow for afterheat cooling. A study o… more
Date: October 16, 1962
Creator: Binford, F.T.; Casto, W.R. & Colomb, A.L.
Partner: UNT Libraries Government Documents Department
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Determination of Heavy Water Purity by Infrared Absorption

Description: The practical application of heavy water purity determination by infrared absorption spectroscopy using standard laboratory equipment was demonstrated in connection with the operation of heavy water-moderated Special Power Excursion Reactor Test (SPERT II) Facillty at the NRTS. (auth)
Date: January 16, 1962
Creator: Abernathey, R. M. & Morgan, T. D.
Partner: UNT Libraries Government Documents Department
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Tests of Bearing Materials for the Experimental Through-Tubes in the Egcr

Description: The four experimental through-tubes provided in the Experimental Gas Cooled Reactor will extend directly through the core of the reactor and penetrate both the upper and lower pressure vessel heads. Each tube is anchored in an upper head nozzle and the bottom end is allowed to slide in a lower head nozzle. This lower nozzle is basically a T'' section that provides bottom access to the through-tube and a side access for the piping which connects the throughtube to the experimenter's cell. Due to… more
Date: July 16, 1962
Creator: MacPherson, R. E. & Smith, A. M.
Partner: UNT Libraries Government Documents Department
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A System for Generating Gamma Ray Cross Section Data for Use with the IBM-7090 Computer

Description: A system for generating detailed tables of gamma ray cross section data has been devised for use on the IBM7090 computer. This sy;tem obviates the preparation of large amounts of cross section data. It also provides a scheme for rapid access to these tabulated values. (auth)
Date: May 16, 1962
Creator: Penny, S. K.; Emmett, M. B. & Trubey, D. K.
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report, November 1961

Description: Openation of a 6-in.-dia foam separation column with Sr/sup 89/ tracer and dodecylbenzenesulfonate as a surfactant and foaming agent was continued. The catalytic oxidation of H/sub 2/, CO, and CH/sub 4/ was studied using a nickel- chromepalladium ribbon catalyst. A Mark I prototype fuel assembly was sheared to within 1.5-in. of the end by modifying the gas hydraulic system of the shear. The force required to shear a highly carburized Mark I fuel assembly ductile tubing. Demonstration of the mec… more
Date: May 16, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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A fast neutron time of flight system for use with cyclotrons

Description: A reference pulse generator, transistorized timedifference-to-pulse- height converter, and beam pulse scaler are described and discussed as to their function in the fast neutron time-of-flight system for use with cyclotrons, The system is used for angular distribution and cross section measurements. Results are presented showing time resolution, absolute counting efficiency, and beam pulse scaling of the system. (N.W.R.)
Date: August 16, 1962
Creator: Fulbright, H. W.; Verba, J. W.; Deshpande, V. K. & Hamann, A. K.
Partner: UNT Libraries Government Documents Department
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Metabolism of C¹⁴-Carboxyl-Labeled-3-Hydroxyanthranilic Acid in Normal and Neoplastic Mice

Description: The o-aminophenol, 3-hydroxyanthranilic acid (3-OHAA) is a metabolite of tryptophan normally present in urine in trace quantities. C14-3-OHAA was given to normal mice and mice with either mammary adenocarcinoma, glioblastoma multiforme or ascites tumor to study the influence of these transplantable tumors on metabolism of 3-OHAA.
Date: February 16, 1962
Creator: Hankes, Lawrence Valentine; Schmaeler, Max & Stoner, Richard D.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: June 1962

Description: This is the monthly report for the Hanford Laboratories Operation June 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.
Date: July 16, 1962
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Special plutonium recycle at Purex

Description: The critical-mass incident at Recuplex has necessitated resumption of reworking Task 1 supernatants through the Purex process. The supernatants contain relatively small quantities of plutonium and will be shipped as treated nitric acid solutions in PR cans. Current plans are to introduce the solutions into the Purex process at the normal rework position, the HAF Make-up Tank E6. This report summarizes the anticipated character of supernatant recycle material, outlines process control requiremen… more
Date: May 16, 1962
Creator: Judson, B. F. & Rathvon, H. C.
Partner: UNT Libraries Government Documents Department
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Production test IP-520-A in-reactor testing with coolant prepared in the water treatment pilot plant

Description: The objective of this test are: (1) to operate two single pass tubes in the 1706-KE in-reactor facility using water treated in the water treatment pilot plant, (2) to obtain samples of effluent water, and (3) to obtain corrosion measurements from weighed fuel, dummies, and coupons.
Date: July 16, 1962
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: March 1962

Description: This is the monthly report for the Hanford Laboratories Operation March 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.
Date: April 16, 1962
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Technical Specifications: Hanford Production Reactors. Revision 4

Description: This report provides technical specifications applicable to the eight operating production reactor facilities, namely B, C, D, DR, F, H, KE and KW (referred to as the Hanford Production Reactors), located at the Hanford Site in the State of Washington. Basic descriptions of the reactor facilities are also contained in the report.
Date: February 16, 1962
Creator: Gilbert, W. D.
Partner: UNT Libraries Government Documents Department
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Critical mass control specification hood 7-A

Description: Hood 7-A will be used to handle filtrate and miscellaneous aqueous waste streams from the RMC button line. This document defines the critical mass control specifications for hood 7-A.
Date: May 16, 1962
Creator: Meeker, L. M.
Partner: UNT Libraries Government Documents Department
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A Comprehensive Study of the Neutron Activation Analysis of Uranium by Delayed-Neutron Counting

Description: The method of neutron activation analysis of U by delayed-neutron counting was investigated in order to ascertain if the method would be suitable for routine application to such analyses. It was shown that the method can be used extensively and routinely for the determination of U. Emphasis was placed on the determination of U in the types of sample materials encountered in nuclear technology. Determinations of U were made on such materials as ores, granite, sea sediments, biological tissue, gr… more
Date: October 16, 1962
Creator: Dyer, F. F.; Emery, J. F. & Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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COMPUTATION OF LOSSES DUE TO MULTIPLE SCATTERING OF CHARGED PARTICLES IN THIN FOILS

Description: The losses of charged particles from a detector aperture, due to multiple scattering of the particles in thin layers of material preceding the detector, are calculated with the aid of a high-speed digitai computer. The rootmean-square multiple-scattering angle is computed after the method of Moliere, and graphs are presented for protons and alpha particles scattering in nitrogen, aluminum, argon, copper, silver, and gold, and for deuterons and tritons scattering in aluminum and copper. The rang… more
Date: May 16, 1962
Creator: Ball, J.B.
Partner: UNT Libraries Government Documents Department
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DESCRIPTION OF A PLUTONIUM AND ENRICHED URANIUM SHIPPING CONTAINER AND INTEGRITY TESTS ON THIS CONTAINER

Description: The M-101 (an all steel) shipping container and safety cage was in use for about 15 years for transporting and storage of enriched U. With slight modifications and the addition of an inner container, the M-101 can be used to ship Pu metal. Various physical tests performed on the M-101 and inner container are described, and critical array sizes under various conditions of spacing and flooding are discussed. (auth)
Date: November 16, 1962
Creator: Schuske, C.L.
Partner: UNT Libraries Government Documents Department
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Progress in Sintering

Description: Sintering is broadly defined as all aspects of the adhesion, densification, shrinkage, and consolidation which accompanies the reduction in surface energy of a powder compact which occurs upon application of heat and/or pressure. The process of sintering is then further divided into the initiation, material transport, and grain growthrecrystallization stages. A general review is made of each of these stages, noting typical work which has contributed to progress in each area involved. (auth)
Date: April 16, 1962
Creator: Wilder, D.R.
Partner: UNT Libraries Government Documents Department
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Application of SNAP 2 to Manned Orbital Space Stations

Description: The results of a study of the installation and operational characteristics of a SNAP reactor system integrated with a manned space station are presented. The reference system selected was an 11 kw(e) version of a SNAP 2 system employing multiple power conversion units coupled to a single reactor source. Of prime importance is the reactor radiation shield required for the manned system and the use of design features which minimize the shield weight. The weight of the radiation shield is highly d… more
Date: December 16, 1962
Creator: Rosenburg, H. N.
Partner: UNT Libraries Government Documents Department
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