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Scale "Up or Down" Analysis for Prototype Test

Description: Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually … more
Date: May 1, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Thorium Isotopes Method for Dating Marine Sediments

Description: This thesis is concerned with a possible method of improving the well-known ionium method of age determination of deep-sea sediment sections (Pet-53, Zou-58, Kul-55, Ran-54) both with respect to accuracy of individual determinations and with respect to the range of applicability of the method.
Date: May 31, 1960
Creator: Almodóvar, Ismael
Partner: UNT Libraries Government Documents Department
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SERVOMECHANISMS WITH FORCE FEEDBACK

Description: A class of linear proportional servomechanisms is examined in which an electrical signal proportional to output force is used to improve performance. The effect of this "force feedback" on a positional servomechanism is analyzed as well as the effect on a special type of servomechanism which reflects load forces back to the input. This latter type of servomechanism is called "force reflecting." Laboratory models of these servormechanisms were designed and constructed, and experimental data are … more
Date: May 1, 1960
Creator: Arzbaecher, R.C.
Partner: UNT Libraries Government Documents Department
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Analog Computer Study of the MSR-ORR in-Pile Pressurized Water Loop No. 1

Description: A study of the dynamic behavior of the Merchant Ship Reactor Pressurized Water Loop was made using the Reactor Controls Analog Facility. Computer curves show the predicted response of the loop temperatures to normal load changes and component failure accidents. Except for complete flow stoppage, which was not investigated here, the safety system was shown to be adequate in curbing loop temperature excursions due to postulated accidents. (auth)
Date: May 1, 1960
Creator: Ball, S. J.
Partner: UNT Libraries Government Documents Department
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Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service

Description: Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date: May 1, 1960
Creator: Baroczy, C. J.
Partner: UNT Libraries Government Documents Department
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Thermal Cycling and Leakage Tests of 12-Inch Valves for Sodium Service

Description: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of valves for use in the sodium coolant system of the Hallam Nuclear Power Facility. Four 12-in. valves were cycled between 680 and 1100 deg F in a sodium loop and periodically tested for across - the-seat sodium leakage. The valves tested were two throttling (ball) valves and two blocking (gate) valves. The first-ball valve had a consistent leakage pattern which vas primarily a functi… more
Date: May 1, 1960
Creator: Baroczy, C. J.
Partner: UNT Libraries Government Documents Department
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Bone Marrow Activity in Vitro Under the Influence of Anemic Serum and Human Erythropoietin

Description: A method is described for observing the uptake of Fe by rat bone marrow cells in vitro. Results of experiments on effects of anemic serum and human erythropoietin are presented with a brief discussion. It is concluded that the differences in uptake of Fe/sup 59/ are the result of isotope dilution. (auth)
Date: May 1, 1960
Creator: Beck, J. S.
Partner: UNT Libraries Government Documents Department
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Phase Diagrams of Zirconium-Beryllium and Related Systems

Description: Introduction. The phase diagram data reported in this paper were obtained during an investigation of the beryllium-metal compounds of the titanium group transition elements. Several compounds in these systems had been previously reported but their compositions and structures were not all known. In the course of this study many details of the phase diagrams of the system were observed. Tentative diagrams consistent with this data will be presented.
Date: May 31, 1960
Creator: Bedford, Ray Gilbert, 1928-
Partner: UNT Libraries Government Documents Department
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Hazards and Experimental Procedure Evaluation for Studies on the Polymerization and Hydrolysis of Plutonium in Uranyl Nitrate and Nitric Acid Solution at Elevated Temperatures

Description: Because of the danger of precipitation of polymerized Pu/sup 4+/, a research program was initiated for studying the polymerization of Pu/sup 4+/ in the UO/sub 2/(NO/sub 3/)/sub 2/--HNO/sub 3/ system. Th e present state of knowledge concerning the polymerization of Pu/sup 4+/ is reviewed, and the program is discussed in detail, including equipment and procedures. The program is evaluated from the viewpoint of hazards, health physics procedures, and personnel safety. (D.L.C.)
Date: May 1, 1960
Creator: Biggers, R E & Costanzo, D A
Partner: UNT Libraries Government Documents Department
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A Multi-Channel Unit of Solid State Counters for Nuclear Spectroscopy

Description: A matrix of twenty 2 x 12 mm squared surface barrier counters has been constructed for use in the image plane of a magnetic spectrometer. The outputs of individual crystals are displayed in predetermined channels of a 100-channel pulse height analyzer. This is done by connecting separate crystals to succession sections of a delay line and converting the time difference between signals arriving at the ends of the line into pulse heights. Simple procedures for producing reliable Ge-Au surface b… more
Date: May 20, 1960
Creator: Bilaniuk, O. M.; Hamann, A. K. & Marsh, B. B.
Partner: UNT Libraries Government Documents Department
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FLUIDIZED-BED COATING OF UO$sub 2$ POWDER WITH NIOBIUM AND OTHER ELEMENTS

Description: The chemical vapor deposition of niobium, molybdenum, tungsten, chnomium, carbcn, and niobium--vanadium alloys in a fluidized bed of UO/sub 2/ powder particles wss used to provide uniform, dense, nonporous coatings on the individual particles. in the case of niobium, which received major attention, hydrogen reduction of niobium pentachloride vapor was used as the vapor- deposition reaction. The most serious problem was that of maintaining bed fluidity aad avoiding agglomeration. This problem wa… more
Date: May 25, 1960
Creator: Blocher, J. M. Jr.; Veigel, N. D.; Oxley, J. H.; Secrest, V. M. & Rose, E. E.
Partner: UNT Libraries Government Documents Department
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Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.

Description: Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-… more
Date: May 27, 1960
Creator: Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
Partner: UNT Libraries Government Documents Department
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Aluminum Alloy Work at Hanford

Description: Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.
Date: May 6, 1960
Creator: Bowen, H. C.
Partner: UNT Libraries Government Documents Department
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A Spectrometer for Study of Neutron Activation of Beryllium-7 as a Function of Energy

Description: Abstract. A neutron diffraction crystal spectrometer with a resolution of 13 microseconds per meter and monochromatic beam intensity up to 10(4)n/cm(2)=sec in the range 0.012-0.400 ev has been constructed for study of the activation cross section of Be7 as a function of energy in the thermal region. First preliminary results using ZnS(Ag) as a detector suggest the possibility of a resonance for the Be7(n,p)Li7 reaction in the region of 0.025-0.050 ev.
Date: May 18, 1960
Creator: Boyer, Walton T., Jr.
Partner: UNT Libraries Government Documents Department
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Mercury Barometers and Manometers

Description: From Abstract: "Sources of error in measuring pressures are described in considerable detail, particularly for portable instruments including scale, temperature , gravity, capillarity, vacuum errors and return gas column. Methods of minimizing those errors and of making the corrections, including extensive tables, are presented."
Date: May 20, 1960
Creator: Brombacher, W. G.; Johnson, D. P. & Cross, J. L.
Partner: UNT Libraries Government Documents Department
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An evaluation of the reactor neutron spectrum

Description: The neutrons in an operating nuclear reactor are generated primarily by the fission events which are taking place. The great bulk of these relatively high energy or fast neutrons are slowed down or thermalized by a series of elastic collisions with the moderator nuclei which comprise the bulk of the volume of the reactor core. Once slowed down, the neutrons diffuse through the reactor core until they are absorbed or eliminated by some other process. Each of these three groups of neutrons, i.e.,… more
Date: May 25, 1960
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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Sr$sup 90$ MONITORING AT THE SAVANNAH RIVER PLANT

Description: Radioassays of milk, soil, grass, and other material located near the Savannah River Plant showed no detectable Sr/sup 90/ due to plant wastes. These assays indicated that the Sr/sup 90/ found in this geographical area (25-mile radius of SRP) was nuclear weapons debris. Sr/sup 90/ was separated from milk by absorption on cation exchange resin. An extraction technique was used in assaying Sr/sup 90/ in all types of samples. Cs/sup 137//Sr/sup 90/ ratios were found to be constant in soil samples.… more
Date: May 1, 1960
Creator: Butler, F.E.
Partner: UNT Libraries Government Documents Department
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In-reactor rupture testing of Zircaloy-2 clad seven-rod cluster fuel elements: Interim report

Description: The high pressure loop installed in the 3X3 reflector position of the ETR and the associated instrumentation to detect and study failure mechanisms handled the rupture tests without difficulty. Failure of the elements was initiated by shearing off a projection on the fuel elements. The first test of the series used previously unirradiated seven-rod clusters. After the projection was sheared off the fuel elements were operated for seven hours with no failure. Failure is defined as having occurre… more
Date: May 3, 1960
Creator: Call, R. L.; Green, J. W. & Kaulitz, D. C.
Partner: UNT Libraries Government Documents Department
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SL-1 ANNUAL OPERATING REPORT FOR FEBRUARY 1959-FEBRUARY 1960

Description: The pericd from February, 1959, when CE assumed operative responsibility of the SL-1 Reactor Plant, to February, 1960 is covered. The operations of the year are summarized; the reactor, instrumentation, mechanical, electrical, and facility systems are evaluated; health and safety, and the operational costing program are discussed. (auth)
Date: May 1, 1960
Creator: Canfield, R. T.; Crudele, J. S.; Vallario, E. J.; Young, R. G. & Rausch, W. P.
Partner: UNT Libraries Government Documents Department
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ABWR QUARTERLY PROGRESS REPORT, JANUARY 1 TO MARCH 31, 1960. VOLUME I. SL- 1 OPERATIONS AND EVALUATION . VOLUME II. SL-1 HEALTH PHYSICS AND SAFETY

Description: The Stationary Low Power Reactor No. 1 is a three Mw boiling water reactor designed to demonstrate the feasibility of a nuclear reactor to supply electrical power and space heat for remote sites. In addition to performance evaluation the facility provides training for military personnel. The reactor was operated for 1159 hr during the quarter for a total core burnup of 20.3%. Power generation was 103.7 Mwd for a total power accumulation of 466.9 Mwd. Eight malfunctions occurred during the quart… more
Date: May 25, 1960
Creator: Canfield, R. T.; Rausch, W. P.; Vallario, E. J.; Young, R. G. & Henderson, S. K.
Partner: UNT Libraries Government Documents Department
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Sub-Cooled Burnout Relative to Hanford Reactors

Description: In the Hanford production reactors, failure of fuel element cladding is known as subcooled burnout since the bulk coolant temperature is below the saturation temperature at time of failure or burnout of the fuel cladding. The heat generation rate at which subcooled burnout occurs, establishes a limit to allowable reactor power level. This document compares present and potential power level limits at the Hanford production reactors with power level limits established by subcooled burnout.
Date: May 31, 1960
Creator: Carlson, P. A. & Trumble, R. E.
Partner: UNT Libraries Government Documents Department
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