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Diffusion Kinetics Studies in the Al-Ni-U System

Description: A diffusion couple technique was developed and standardized for the purpose of obtaining meaningful data regarding the diffusion kinetics of the Al-- Ni--U system. The technique entailed hot pressing under a dynamic vacuum and subsequent isothermal soaking treatments within evacuated quartz tubes for periods of 10 to 7000 hr at temperatures of 850, 750, 850, andd 950 deg F. In addition, the nickel barrier bond between Type 1100 aluminum cladding and cast U- 3.5% Mo fuel alloy was metallographic… more
Date: November 30, 1963
Creator: Harlow, R. A. & Gamba, O.
Partner: UNT Libraries Government Documents Department
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FLOW CONTROLLER EVALUATION FOR SODIUM SERVICE

Description: Tests were conducted to evaluate the performance of a 10-in. flow controller in sodium at temperatures up to 1200 deg F. Torque tube reliability was determined by extensive mechanical cycling tests and further checking with a helium mass-spectrometer leak detector. Flow control performance and valve vibration characteristics were tested and evaluated and flow rate limits were established. The valve assembly was subjected to a thermal shock test program simulated to represent the most severe con… more
Date: November 30, 1963
Creator: Winborne, R.A.
Partner: UNT Libraries Government Documents Department
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MOUND LABORATORY PROGRESS REPORT FOR NOVEMBER, 1963

Description: As a part of the effort to establish the vapor pressure of /sup 3/He as the international temperature scale between 0.3 and 3.2 deg K, the manometric contections from /sup 4/He to /sup 3/He are being determined. The results of a single run did not agree with the predicted values. Calculations indicated that a two to one thermal diffusion column cascade is more efficient than a three to one cascade for separation of neon isotopes. Gaseous impurities in neon were reduced from 3.40 to 0.26% by pas… more
Date: November 30, 1963
Creator: Eichelberger, J.F.; Grove, G.R. & Jones, L.V.
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: November 30, 1963
Creator: Auleta, J. J.
Partner: UNT Libraries Government Documents Department
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INSTRUMENT FOR DETERMINING CRUSHING STRENGTH OF PARTICLES

Description: An instrument for crushing-strength determinations of uncoated and pyrolytic-carbon-coated fuel particles (50 to 500 mu in diameter) was developed to relate the crushing strength of the particles to their fabricability. The instrument consists of a loading mechanism, load cell, and a power supply-readout unit. The information that can be obtained by statistical methods of the data analysis is illustrated by results on two batches of fuel particles. (auth)
Date: November 29, 1963
Creator: Hallerman, G. & Gray, R.J.
Partner: UNT Libraries Government Documents Department
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Comparative reactor flux spectra

Description: This document is explanatory in nature and is intended to clarify certain questions about reactor neutron flux spectra in various AEC production facilities. Simplified models are used to illustrate neutron ``temperature,`` spectral ``hardening,`` and the so-called ``Westcott R.``
Date: November 27, 1963
Creator: Gumprecht, R. O.
Partner: UNT Libraries Government Documents Department
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Non-Destructive and Destructive Transient Tests of the Spert I-D, Fully Enriched, Aluminum-Plate-Type Core: Data Summary Report

Description: This report is a documentation of the experimental data from each test of the series performed in the Spert I reactor with the type D, fully enriched, aluminum plate-type core. The series of tests consisted of step-wise insertions of excess reactivity under conditions of ambient temperature and atmospheric pressure. The data obtained from each test are presented in tabular form and as plots of the time behavior of reactor power, fuel plate surface temperature, and pressure. Composite figures, d… more
Date: November 27, 1963
Creator: Zeissler, M. R.
Partner: UNT Libraries Government Documents Department
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Amines as Extractants--Survey of the Descriptive and Fundamental Extraction Chemistry

Description: Both the study and the use of extractions with highmolecular-weight amines (including quaternary ammoniums) in organic solution are increasing extensively. While equilibria have been measured in the extraction of an increasing range of acids and Aetal ions, a difficulty remains unresolved in that the amine concentration powerdependence of extraction often indicates a different stoichiometry of the complex existing in the organic phase than do limiting loading and other considerations. Neverthel… more
Date: November 26, 1963
Creator: Coleman, C. F.
Partner: UNT Libraries Government Documents Department
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Preliminary study of multiple fuel processing at the Purex Plant

Description: Processing of multiple types of irradiated fuel elements in Purex has been proposed to the Atomic Energy Commission as a means of realizing significant savings in overall CPD operating costs for weapons programs and permitting release of the Redox plant for non-weapons programs. The process and equipment requirements for implementing a multipurpose operations program have been under study in both plant and laboratory programs for processing slightly enriched Zircalloy-clad uranium metal fuels a… more
Date: November 26, 1963
Creator: Kendall, J. B.; Lambert, R. W. & Nielson, S. M.
Partner: UNT Libraries Government Documents Department
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Annual Progress Report on Fuel Element Development for Yy 1963

Description: Progress in fuels and materials development is reported. Irradiation tests on powdered UAl/sub 3/ intermetallic compounds demonstrated good stability and fission gas retention capabilities. Developmental aluminum powder metal products showed good corrosion resistance at high temperatures while retaining excellent high temperature strength. All of the fuel compositions tested (UO/sub 2/, U/sub 3/O/sub 8/, and UAl/sub 3/ in aluminum matrices) exhibited density decreases under irradiation. Tensile… more
Date: November 25, 1963
Creator: Gibson, G. W.; Graber, M. J. & Francis, W. C.
Partner: UNT Libraries Government Documents Department
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Destructive Examination of a SNAP Heat Source

Description: A detailed examination was made of one of three plutonium-238 fueled SNAP 3 heat sources which was shipped from Mound Laboratory in May 1961 and returned in May 1963,. Examination of source included radiography, calorimetry, dimensional inspection, radiation measurements, internal pressure measurements, metallographic examinations of the containers, and recovery and impurity analysis of the plutonium fuel. Results showed that the inner tantalum container of the source failed at the weld, allowi… more
Date: November 25, 1963
Creator: Wyder, W. C.; Powers, J. A. & Vallee, R. E.
Partner: UNT Libraries Government Documents Department
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Analysis and evaluation of the N Reactor Zone Temperature Monitoring System

Description: This document reports the result of an engineering analysis and evaluation of the Zone Temperature Monitoring System. The main function of the system is to protect the reactor from localized increases in reactor power which would be reflected by increases in the tube outlet temperatures in the affected zones of the reactor. This function has been implemented by the installation of immersion temperature detectors on 109 representative process tubes. The signals from the detectors will be monitor… more
Date: November 22, 1963
Creator: Philipp, L. D.
Partner: UNT Libraries Government Documents Department
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THE RECOVERY OF MECHANICALLY ENTRAPPED PLUTONIUM FROM CASTING SKULLS AND TURNINGS

Description: The small critical mass of plutonium which limits charge size, coupled with its value necessithting quantitative recovery from all residues, makes the direct recovery of mechanically entrapped plutonium from casting skulls and oxidized turnings an economic necessity. The newest method used at the Los Alamos Scientific Laboratory for the direct recovery of entrapped plutonium involves mechanical stirring and vibration of the plutonium melt to physically break up to spongy skull and oxide film, t… more
Date: November 22, 1963
Creator: Harbur, D.R.; Romero, J.W. & Anderson, J.W.
Partner: UNT Libraries Government Documents Department
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Analysis of E-N target conversion data

Description: Production efficiency studies of the E-N loading require that conversion ratio values for both plutonium and tritium be defined. Changing of the core-loading charge makeup with each core load to obtain a more efficient loading has theoretically resulted in increasing the tritium conversion ratio. Tritium recovery data from the third H Reactor E-N loading has recently become available for analysis. The buildup of product is much slower in fringe blanket material then in core target pieces. The s… more
Date: November 21, 1963
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: October 1963

Description: This report, for October 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: November 21, 1963
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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PRELIMINARY DESIGN OF SRE-PEP CORE III VARIABLE ORIFICE

Description: A single, wide-range variable orifice design is developed, which provides a maximum orifice flow area of 2.0 in./sup 2/ and a minimum oriflce flow area of 0.2 in./sup 2/ The design is based on an overall operating core DELTA P of 4.0 psi and provides for a sodium flow range of 2.45 to 10.0 lb/sec. Bypass leakage around the orifice is analyzed and accounted for in the design. It is shown that the use of piston rings is not necesary to reduce this leakage. The orifice plug profile is calculated f… more
Date: November 21, 1963
Creator: Noyes, R.C.
Partner: UNT Libraries Government Documents Department
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Buckling Measurements : Heavy Natural Uranium Tubular Fuel Assemblies

Description: One-region buckling measurements that were made on a series of D/sub 2/O- moderated lattices of heavy uranium metal tubes in the Process Development Pile at Savannah River Laboratory are presented. The purposes of these measurements are to provide normalization points for lattice bucklings and to extend the study of natural uranium- D/sub 2/O systems. The dependence of buckiing on the moderator-to-fuel ratio is studied for two types of lattices.
Date: November 20, 1963
Creator: Dunklee, A. E. & Graves, William E. (William Ernest), 1941-
Partner: UNT Libraries Government Documents Department
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