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LITHIUM HYDRIDE PROPERTIES

Description: A tabulation is presented of values for selected properties of lithium hydride. (M.C.G.)
Date: March 14, 1961
Creator: Welch, F.H.
Partner: UNT Libraries Government Documents Department
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A Method of Determining the Intermediate Energy Neutron Dose

Description: The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediat… more
Date: March 10, 1961
Creator: Hankins, D. E.
Partner: UNT Libraries Government Documents Department
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A METHOD FOR RECORDING NUCLEAR RESONANCE CAPTURE SPECTRA

Description: A method is described for continuously varying the Van de Graaff ion beam energy while the count rate from the decay of the compound nucleus is monitored and recorded. The method utilizes a synchronous motor system to synchronize the recorder and the magnetic field control of the Van de Graaff analyzing system. Use of this method results in significant time saving in calibration of the Van de Graaff accelerator and the determination of target thicknesses. (auth)
Date: March 1, 1961
Creator: Jeter, T R & Baldeschwieler, J D
Partner: UNT Libraries Government Documents Department
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Air Pulser for H-1 Column

Description: Studies the prototype and production air pulse units.
Date: March 1, 1961
Creator: Bruns, L.E.
Partner: UNT Libraries Government Documents Department
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Calculation of Doppler Coefficient and Other Safety Parameters for a Large Fast Oxide Reactor

Description: Several safety parameters are calculated for a large, fast, Na-cooled, oxide-fueled reactor. The Doppler coefficient is studied as regards its effect on the reactivity during a power excursion, and its dependence on the neutron spectrum, on the concentrations of U/sup 238/, Pu /sup 239/ , a nd Pu/sup 240/, on spatial temperature and power distributions, and on temperature. Other parameters studied include the Na temperature coefficient of reactivity, and the reactivity insertion caused by total… more
Date: March 23, 1961
Creator: Greebler, P.; Hutchins, B. A. & Sueoka, J. R.
Partner: UNT Libraries Government Documents Department
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Suitability of Inconel for Corrosion Protection on Water Side of Sodium Component Steam Generator

Description: The heat exchanger and steam generator for the U. S. Atomic Energy Commission Sodium Components Project will be constructed entirely of type 316 stainless steel. Because of the susceptibility of this alloy to stress corrosion cracking, it is proposed to clad all areas of the steam generator with Inconel where the stainless steel will be exposed to water and steam. A discussion is presented of the work to justify the selection of Inconel for this service. A discussion of Inconel type welding all… more
Date: March 1, 1961
Creator: Phillips, L. E. & Vawter, F. F.
Partner: UNT Libraries Government Documents Department
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The Cold Pressing of Sinterable UOâ‚‚

Description: The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date: March 27, 1961
Creator: Levey, R. P., Jr.
Partner: UNT Libraries Government Documents Department
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Feasibility Study of a New Mass Flow System : Quarterly Report No. 3 Covering the Period from December 1, 1960 to February 28, 1961

Description: This is the third quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: March 20, 1961
Creator: Burgwald, G. M.; Stone, C. A. & Genthe, William K.
Partner: UNT Libraries Government Documents Department
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High-Temperatuer Creep Evaluation in Carbon Dioxide Atmosphere : Summary Report, October 1, 1959 to March 31, 1961

Description: This report follows an investigation made to determine creep-rupture data for three sheet materials. Fourteen of sixteen tests were made in an atmosphere of carbon dioxide within hermetically sealed capsules, analyzing the reaction of the three sheet metals: 347 stainless steel, iron-aluminum-chromium alloy designated 261C, and a zirconium-base alloy, AE1H. Minimum creep rate, per cent elongation, and rupture life were determined and reported.
Date: March 31, 1961
Creator: Domagala, R. F.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: February 1961

Description: This is the monthly report for the Hanford Laboratories Operation, February 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: March 15, 1961
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Production test IP-402-A, Irradiation of Zr-2 cladding studies capsules

Description: The objective of this production test was to evaluate the effects of Zr-2 jacket uniformity, thickness, and temperature on non-uniform clad straining. Test details are provided.
Date: March 24, 1961
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Maximum liability evaluation: Strontium and cesium shipments on Decalso media

Description: This report summarizes the evaluations of the maximum monetary liability associated with cesium-137 shipments in the STT Casks and strontium-90 shipments in the HAPO-IA Cask. These evaluations are of most immediate importance since these shipments are planned for the month of March 1961. These liability evaluations concern the direct consequences of a release of the fission product shipment in each case, but do not cover the probability of such events occurring. The liability evaluation of the … more
Date: March 13, 1961
Creator: Watson, E. C. & Zahn, L. L.
Partner: UNT Libraries Government Documents Department
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Re-evaluation of metal performance levels of C-II-N and C-II-E material

Description: This report presents an analysis of rupture experience at C Reactor over the past two years. The purpose of the study was to provide a basis for revising, if necessary, the current metal performance level multipliers for C-II-N and C-II-E material.
Date: March 3, 1961
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Production test IP-401-A: Irradiation of Zircaloy-2 jacketed UO{sub 2} tubular elements in the KER loops

Description: The objective of this production test is to evaluate the behavior of large diameter tubular UO{sub 2} fuel elements during high temperature irradiation. Eighteen inch long tubular UO{sub 2} fuel elements 1.804 inch OD, 0.544 inch ID, in 0.060 inch Zircaloy-2 jackets will be irradiated in the KER loops either alone or in conjunction with other tests to exposures up to 3500 MWD/T of contained uranium.
Date: March 16, 1961
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Research project, Contract CA-264, chemical milling of counterbore recesses in the uranium wall of Zircaloy-2 clad uranium tubes. Final report

Description: This document provides the final report on the research project of chemical milling of counterbore recesses in the uranium wall of Zircaloy-2 clad uranium tubes. The scope of work, results and conclusions, and experimental procedures are provided.
Date: March 28, 1961
Creator: Atkins, D. C. Jr.
Partner: UNT Libraries Government Documents Department
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105-C overboring thirteen tube outage, March 6, 1961--March 10, 1961

Description: C Reactor was shut down on a scheduled basis at 8:30 a.m. March 6, 1961 for the purpose of overboring 17 process channels. this report will cover that outage and discuss problems encountered in completing the tasks involved in overboring.
Date: March 24, 1961
Creator: Munro, C. A.
Partner: UNT Libraries Government Documents Department
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Review material for reactor physics primer

Description: This report contains questions and answers on topics in reactor physics.
Date: March 1, 1961
Creator: Lockwood, E. H.
Partner: UNT Libraries Government Documents Department
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IPD predicted vs CPD measurement differences twelve two-ton test batches

Description: This report summarizes the IPD predicted vs. CPD measured values from twelve two-ton test batches. Two sets of comparisons are provided: CPD measured vs. IPD predicated based on techniques used since January 1, 1960 and CPD measured vs. IPD predicted based on techniques used prior to January 1, 1960.
Date: March 29, 1961
Creator: Hoba, D. W.
Partner: UNT Libraries Government Documents Department
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Production test IP-338-A: DR-reactor heat decay test at high outlet water temperatures

Description: This test is designed to obtain up-to-date information on heat decay values following a reactor scram. More specifically its purpose is to determine the effect of increased outlet water temperatures upon this heat output value. A recent review of the ``last ditch`` cooling system at the Hanford reactors indicated that at some reactors this backup coolant supply did not meet our coolant adequacy criteria at certain critical times after the loss of electric and steam pumping power. On the basis o… more
Date: March 6, 1961
Creator: Jones, S. S.
Partner: UNT Libraries Government Documents Department
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Post irradiation examination of elliptical fuel element (RM-416)

Description: During the post-irradiation measuring of fuel elements from PT-IP-262A by, Component Testing Operations, Irradiation Processing Department, one element exhibited 0.069 inch of diametric ellipticity. The element had been fabricated from natural uranium, clad in X-8001 aluminum alloy, and was internally and externally cooled during irradiation. The element was selected for detailed examination to determine the cause of the distortion and was transferred to the Radiometallurgy Laboratory in Januar… more
Date: March 1, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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A Reliability Improvement Program Planning Report for the SNAP 10A Space Nuclear Power Unit

Description: The estimated achieved reliability of SNAP 10A space nuclear power units will be relatively low at the timeof the first SNAPSHOT flight test in April 1963 and the existing R&D program does not provide a significant reliabiity growth thereafter. The total costs of an 8-satellite network using SNAP 10A units over a 5-year period has been approximated for the case where the total cost of a single satellite launched is 8 million dollars.
Date: March 14, 1961
Creator: Coombs, M. G.; Smith, C. K. & Wilson, L. A.
Partner: UNT Libraries Government Documents Department
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BETTIS TECHNICAL REVIEW. REACTOR TECHNOLOGY

Description: Developments at the Bettis Laboratory in the area of reactor technology are reported. Seven papers are included for which separate abstracts are prepared. (J.R.D.)
Date: March 1, 1961
Partner: UNT Libraries Government Documents Department
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PERIODIC WASTE DISPOSAL SYSTEM MATERIAL BALANCE TEST. CORE I, SEED 2. Section 2. Test Results T-641317

Description: ABS>A test was made on the Radioactive Waste Disposal (RWD) system to determine the acceptability of procedures used in containing, processing, and disposing the wastes received from the plant during a steady-state operation. The RWD system was found to be adequate and to have 60,000 gallons available at all times in the Surge and Decay tanks for safety injection. (D.L.C.)
Date: March 17, 1961
Partner: UNT Libraries Government Documents Department
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