Technical Report Archive & Image Library (TRAIL) - 789 Matching Results

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Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis

Description: The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly apparent in the analysis of syste… more
Date: November 30, 1959
Creator: Love, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Technical Report on Physics Research

Description: Results are summarized on theoretical considerations of the excited states of the Ca isotopes, experimental studies of the level structure of Ca42 and Ca44, studies of the production of circularly polarized bremsstrahlung by beta rays, the Moller scattering spectrometer, and the Moller scattering coincidence experiment.
Date: November 30, 1959
Creator: McCullen, J. D.; Kraushaar, J. J.; Woolum, J. C.; Sandifer, C. W.; Kliwer, J. K.; Baker, D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Leveling of Extraction Tool Crane Rails. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-246, FY-59-323

Description: The purpose of the test was to check the extraction crane rails in the area of the reactor pit for level and parallelism. The west extraction crane rail exceeded the allowed tolerance of 1/32 inch at only one location. The elevation of the north bumper was out of tolerance by 1/64 inch. The east extraction crane rail was consistently lower than the west rail by as much as 8/64 inch. The east rail was parallel with the west rail within allowable tolerances over the length tested except at one lo… more
Date: November 30, 1959
Creator: Pazuchanics, Nicholas
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section III. First Performance. Core I, Seed 1. Test Results DL-S-231, T-612394

Description: The purpose of the test was to determine the radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown following plant power operation. Radiation levels at the survey points in the 1-AC and 10BD Boiler Chambers Enclosures and in the Reactor Container Enclosure indicated that no significant radiation hazards were present approximately 25 minutes after all rods had been inserted. The radiation levels approximately 4 minutes after shutdown at the surve… more
Date: November 30, 1959
Creator: Shramko, John, Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SM-2 Critical Experiments : CE-1

Description: Abstract: Critical experiment studies were performed, varying the parameters U235, B10 and metal to water ratio, in the SM-2 7 x 7 core configuration with 38 stationary elements and seven control rods of the SM-1 (APPR-1) type. An experimental mock-up of the SM-1 was assembled using the basic SM-2 fuel plates. Excellent agreement between the SM-1 boron loading, determined by chemical analysis, and the SM-1 mock-up boron loading, for equivalent bank positions, was noted. Several SM-2 mock-ups, … more
Date: November 30, 1959
Creator: Noaks, J. W.; McCool, W. J.; Robinson, R. A.; Schrader, E. W. & Weiss, S. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SRE Fuel Element Damage: An Interim Report

Description: Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date: November 30, 1959
Creator: Jarrett, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Time Variation of Thermodynamic Parameters of a Gas in the Region of a Shock Front : Progress Report III

Description: The original goal of this investigation was to compare the thermodynamic characteristics of the gases in and behind the shock fronts in gases at initial pressures in the millimeter range and to compare these characteristics in the geometries of single and double discharges. The shock fronts were not visible, so it was not possible, at these pressures, to get visual data from the shock front itself. The parameters giving the properties of the gases were faces. Measurements made with an image con… more
Date: November 30, 1959
Creator: Eastmond, E. John (Elbert John), 1915-; Hales, Richard Wayne, 1926-; Hoyt, G. D.; Baird, Ramon C.; Chowdhury, P. N. R. & Strong, William J
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Decontamination of the KER Rupture Experiment Loop. Test Series B - Tests No. 3. Test Series D-Test No. 1.

Description: The first series of tests in the KER-REP-1 loop proved that a fission product contaminated loop could be decontaminated to a safe level for contact maintenance. Since a good decontamination process was available, there was much that could be improved about this process. Further testing of this process and several variations of other processes have been scheduled. The evaluation of these processes includes specific decontamination factors, process corrosion, and loop activity reduction factors (… more
Date: November 25, 1959
Creator: Weed, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Possible Failed Blanket Elements Using the FEDAL System. Section I. First Performance. Core I, Seed 1. Test Results DL-S-2810S, RNI-24

Description: The purpose of the test was to determine if failed blanket elements exist in other regions of the core beside F-2. FEDAL sampling ports that have indicted the greatest deviation as determined in a statistical analysis performed on a number of traverses in the FEDAL system will be tested. Data obtained from the start up runs of the FEDAL sample port Nos. 11, 31, 36 and 37 of Monitor 2 and port Nos. 14, 46, 11, 49 and 7 of Monitor 1 gave no indications of a blanket element failure. At each power … more
Date: November 23, 1959
Creator: Pazuchanics, Nicholas & Kearns, Walter
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Present Status of Semiconductor Particle Counters

Description: This review lists some of the salient features of semiconductor particle counters and cannot claim to contain an exhaustive listing of all the work in the field. Performance results on the surface-barrier counters as developed at California Institute of Technology are included as typical for this type of counter, though comparable results have been obtained elsewhere.
Date: November 23, 1959
Creator: Barnes, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity Lifetime. Section I. Third Performance. 2797-3797 EFPH. Core I Seed I.

Description: The PWR Plant was operated at approximately 60 MW net electrical output for a total of 1000 EFPH from February 3, 1959 to March 28, 1959. During this period, while performing DL-S-225, there were two planned shutdowns, no safety shutdowns or safety insertions and one flux title. The performance of the plant was satisfactory during the period of the test.
Date: November 23, 1959
Creator: Lawrence, Roger J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Shielding Efficiency of Heavy Element Neoprene Gloves at Low X-Ray Energies

Description: The utilization of gloves wherein heavy element additives have been included is a significant means of reducing exposure to hands and, consequently, increasing allowable working time in operations which require direct contact with low energy isotopes - such as plutonium. The number of such gloves available has been limited considerably by the feasibility of fabrication and the practicality of application. The following study was made on two basic gloves - the first, a heavy zinc-neoprene coated… more
Date: November 23, 1959
Creator: Mehas, T. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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1A Reactor Inlet Hydraulic Valve Position Detector Temperature. Section I. Core I, Seed 1. Test Results DL-S-258-S, RNI-3

Description: The purpose of the test was to determine the internal temperature of the valve position detector for the 1A reactor inlet hydraulic valve with the plant at normal pressure and temperature and at power. The normal operating temperatures for the valve position detector on the 1A reactor inlet hydraulic valve range from a minimum of 287 F to a maximum of 294.7 F.
Date: November 20, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Diffusion of Xenon in Columbium

Description: The diffusion coefficient was calculated for the diffusion of Xe through Nb and found to be 0.064 exp (-18,600/RT).
Date: November 20, 1959
Creator: Gregory, D. P. (Derek P.) & Leavenworth, H. W. (Howard W.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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On the Dynamic Design of Non-Regenerative Transistor Circuits : Report No. 94

Description: In this technical report, firstly, the transfer function of a non-regenerative, base-driven transistor circuit is derived by applying the linear equivalent circuit method. The results are experimentally verified. Secondly, the idea of the inverse-gain-bandwidth is introduced as the criterion of the dynamic design. Thirdly, the stability factor is explained. Finally, it is shown that a system constructed by various types of transistor switching circuits is reduced to a long train of unit chains … more
Date: November 19, 1959
Creator: Kunihiro, Toshiro
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control Air Conditions at the Reactor Chamber. Section I. Test Results DL-S-269

Description: The purpose of the test was to determine the ability of the Control Air System to provide the necessary quantity and quality of clean, dry air to keep the rod drive mechanism stator and position indicator housings at about 3 PSIG in order to avoid low stator resistances resulting from condensation during plant cooldown. The Control Air System is capable of providing the quality of air specified in AEC letter SBO:JWF:100 dated November 17, 1958 of less than 44 grains of moisture per lb. of air i… more
Date: November 18, 1959
Creator: Eckenrode, Gerald E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Core I Control Rod Drive Mechanisms Periodic Tests. Section I. Ninth Performance. Test Results DL-S-148-I, T-550011

Description: The purpose of the test was to determine the operating conditions of the rod drive mechanisms so that operating personnel may be informed concerning malfunctioning mechanisms. The results the this test favorably agree with previous results. The operating characteristics of the rod drive mechanisms checked in this test have not changed appreciably.
Date: November 18, 1959
Creator: Pazuchanics, Nicholas
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High-Speed Saw Tests Power Reactor Fuels Reprocessing Development

Description: The basic scheme for processing power reactor fuels at Hanford includes the removal of inert endfittings ("hardware") from the active sections of the fuels. Within Hanford Laboratories, research and development studies have been in progress on various types of saws which might be used for hardware cutoff. In the initial phase of the program, high-speed saws were investigated; more recently, studies on low speed saws have been conducted. This report summarizes the high speed saw studies and incl… more
Date: November 18, 1959
Creator: Kelly, V. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurements of Coefficients of Reactivity. Section I. Seventh Performance. 3032-EFPH. Core I, Seed 1. Test Results DL-S-151 (T-550132)

Description: The purpose of the test was to determine the temperature and pressure coefficients of reactivity at zero power. Data was obtained during this test which indicates a new temperature coefficient and a pressure coefficient corrected to station operating conditions of 500 F and 1785 PSIG.
Date: November 18, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Station Radiation Level Survey. Section II. Fifth Performance. Core I, Seed 1. Test Results DL-S-157

Description: The purpose of the test was to determine the level of the radiation field in the Turbine Plant during a significant power run. The initial power level survey had an average radiation level of 0.02 mr/hr. this survey showed and average radiation level of 0.03, which was considered background level. this radiation level was far below the maximum allowable level of 2 mr/hyr. No Neutrons were detected.
Date: November 18, 1959
Creator: McTish, James M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Investigation of Autoclave Failure

Description: On July 31, 1959, an autoclave ruptured while being used for thermal cycling studies of Plutonium Recycle Test Reactor (PRTR) plutonium-aluminum fuel elements. Since stand-in materials were being used in this test, no contamination was involved. This accident could lead to inference of greater hazards associated with PRTR fuel designs than had previously been postulated. An ad hoc technical investigation committee was appointed by the Manager Reactor and Fuels Research and Development, to stud… more
Date: November 18, 1959
Creator: Wittenbrock, N. G.; Freshley, M. D.; Griggs, B. & Wheeler, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Magnetic-Force Resistance Butt Wielding of Zircaloy-2 Fuel Element Closures

Description: Zircaloy-2 has a strong tendency to absorb oxygen and nitrogen at elevated temperatures. These gas impurities are extremely harmful, causing brittleness and loss of corrosion resistance. The production of ductile corrosion-resistant welds by present methods required shielding of the weld metal by an inert gas atmosphere or by a vacuum. The alternative to an inert gas atmosphere or a vacuum is reduction of the welding time to a few milliseconds of time to prevent gas absorption.
Date: November 16, 1959
Creator: Mills, L. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hot-Pressure Bonding of OMR Fuel Plates

Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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