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Climatic Charts and Data of the Radio Refractive Index for the United States and the World

Description: From Introduction: "This Monograph has as its purpose the compilation and analysis of the extensive radio refractive index data available within the Central Radio Propagation Laboratory of the National Bureau of Standards. This will be accomplished by presenting both tabulations of basic data for specific locations and charts for interpolation to any location."
Date: November 25, 1960
Creator: Bean, B. R.; Horn, J. D. & Ozanich, A. M., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Sodium Graphite Reactor: Tommorrow's Power Plant

Description: A description is given of the Advanced Sodium Graphite Reactor Power Plant, including the reactor, heat transfer systems, generatirg plant, control systems, and the economics of producing 256 Mw(e). The safety of this design is due to its unusually low operating pressure, absence of chemically incompatible materials in the core, and excellent stability under atatic and dynamic conditions. The reactor is being constructed at Hallam, Nebraska, at a probable cost of 0 to 0/kw, exclusive of the fir… more
Date: April 25, 1960
Creator: Beeley, R. J.; Lowell, E. G.; Polak, H. & Renard, J.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recommendations to apply the ``square pile`` total control concept

Description: It is recommended that the ``square pile`` concept be adopted for all disaster total control calculations, and that the basic reactor constants listed in HW-62884, except for Ball 3X local strength at the DR Reactor, be used in applying this method. Curves are included for each reactor type, indicating allowable enrichment based on appropriate local control strengths. (The reactors whose operating methods are affected by disaster total control requirements are B, D, F, and DR Reactors; the rema… more
Date: February 25, 1960
Creator: Bowers, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ALUMINA COATING OF UO$sup 2$ SHOT BY HYDROLYSIS OF ALUMINUM CHLORIDE VAPOR

Description: Uniform, dense coatings of alumina about 5 to 150 mu thick were applied to uranium dioxide particles 44 to 350 mu in diameter by hydrolysis of aluminum chloride vapor in a fluidized bed of the particles at 1830 deg F. The coated particles were resistant to nitric acid leaching, to oxidation in 1830 deg F air, and to thermal cycling from 6OO to 2500 deg F. After low neutron exposures, the coated particles showed excellent fission-gas retention at temperatures up to 2400 deg F in inert gas. Altho… more
Date: October 25, 1960
Creator: Browning, M. F.; Veigel, N. D.; Cook, T. E.; Diethorn, W. S. & Blocher, J. M., Jr.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proposal for charging the fifth rupture fuel experiment: GEH-10, 34, 35

Description: The objective of this irradiation is to further verify the corrosion rate of tubular-type fuel elements under conditions of high specific power and central core temperatures. This fuel will be the inner tube only of an NPR fuel assembly. As in previous tests, this inner tube rupture will be used to further substantiate the rupture detection instrumentation that is being used in the development of the NPR. Previously unirradiated fuel will be used in this test. The reactor is to operate at full … more
Date: August 25, 1960
Creator: Call, R. L. & Kaulitz, D. C.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Temperature Distribution Moderator and Reflector Reactor Core. Experimental Gas Cooled Reactor

Description: A study was made to determine the coolant flow required to prevent the temperature of the graphite moderator and reflector blocks from exceeding 1100 deg F at full-power operating conditions. The temperature distribution in the graphite blocks was also determined. Tha moderator was primarily cooled by coolant flowing in the 1/8-inch annulus formed by the fuel-assembly sleeves and the fuel-channel holes in the moderator blocks. Coolant flow in the controlrod channels and in the experimental-tube… more
Date: April 25, 1960
Creator: Cheng, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pb-Sn Alloy Replacements for UO2 Density Standards

Description: A correlation between the optical densities if the Pb-Sn alloy system and UO2 with respect to Co^60 gamma radiation has been determined. This enables one to fabricate density standards of whatever geometry may be desired for one in the gamma absorptiometer by simply casting a Pb-Sn alloy of the proper composition to correspond to the density required.
Date: April 25, 1960
Creator: Christensen, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Oxygen Removal with Hydrazine- Interim Report

Description: During normal operation the NPR will function as a closed system and the coolant will be maintained at a high degree of purity. Periodically, however, the system will have to be opened for fuel element discharge and/or decontamination. During these periods the reactor will be operated on single pass cooling. The use of deionized and deoxygenated water as the single pass coolant is not economically feasible due to the large quantities of coolant that will be required. At present it appears that… more
Date: January 25, 1960
Creator: Demmitt, Thomas F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Report on pH Control by Ion Exchange in High pH Systems

Description: The primary purpose of a cleanup system in a recirculating water loop is to maintain the best possible water quality conditions. This is normally accomplished by continuously purifying all or a portion of the coolant. A secondary objective of the cleanup system is to help maintain the system pH at a constant value. A system that will satisfactorily accomplish both of these objectives is at times difficult to obtain. Generally the pH control characteristics are sacrificed in favor of the more im… more
Date: April 25, 1960
Creator: Demmitt, Thomas F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Qualification Approval Tests on resistance products Co.`s type {open_quotes}H{close_quotes} Carbon Composition resistors (0.2 and 40 Megohm)

Description: Engineering Work Requests ESE-48 & 49 established a program for performance of Qualification Approval Tests on RPC`s 0.2 and 40 meghom Carbon Composition Resistors. This report is an accounting of these tests wherein (50) samples of each component were subjected to QA tests per drawings 8O2C250 and 802C251. Tests are explained and results tabulated.
Date: March 25, 1960
Creator: Dixon, L.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Contraction Losses and High Temperature Pressure Drop Determinations for Tube Bundles

Description: In some engineering applications it has become necessary to operate equipment containing small diameter rods or tubes oriented parallel to flow stream. In the case of several nuclear reactors such as the Plutonium Recycle Test Reactor and the S. S. Savannah Maritime Reactor, bundles of small diameter rods are used as the fuel elements. The situation also has application to heat exchangers. A method for accurately predicting the pressure drop characteristics of various bundle configurations woul… more
Date: January 25, 1960
Creator: Gartin, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extended hydraulic demand curves for K geometry tubes with I&E fuel elements

Description: Steady state hydraulic demand curves were obtained for tube powers of 500, 1000, 1500 and 2000 KW with an inlet water temperature of 20C and a rear header pressure of 25 psig. These curves are shown in figures. The point of initial unstable flow for various tube powers is shown for a front header pressure of 325 psig. The flow rate that would lead to the initial point of unstable flow as a result of a sudden plug upstream of the Panellit tap is shown in a figure.
Date: February 25, 1960
Creator: Hesson, G. M.; Fitzsimmons, D. E. & Kanninen, M. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HIGH CURRENT SATURATION CHARACTERISTICS OF THE ORNL COMPENSATED IONIZATION CHAMBER (Q-1045)

Description: The saturation voltage and current characteristics of a compensated ionization chamber (Q-1045) were measured with special regard to high current and voltage ranges. The chamber can be operated at currents up to I ma with a 2000 volt power supply. (auth)
Date: May 25, 1960
Creator: Kaufman, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pulsed Neutron Measurement of Control Rod Worth

Description: Reactivity measurements made by the pulsed neutron technique were compared with results obtained by conventional techniques. The pulsed neutron results were in good agreement with those obtained by stable period measurement and rod drop. Differential effectiveness of partially inserted rods was shown to be well represented by elementary perturbation theory. Finally, the pulsed neutron technique was found to be the only good method for measurement of large reactivity changes.
Date: August 25, 1960
Creator: Kolar, O. C. & Kloverstrom, F. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Some Properties of Vanadium Group Beryllides

Description: Vanadium group beryllides were prepared and studied by x - ray powder diffraction and crystallographic methods. Properties included phase studies, sintering studies, vapor pressure measurements, and thermal diffusivity measurements,
Date: May 25, 1960
Creator: Krikorian, Oscar Harold
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plowshare Program : Peaceful Uses for Nuclear Explosives

Description: The concept of thermonuclear explosives as a potentially cheap and almost inexhaustible energy source for mankind's non military needs has for several years been under active consideration at the Lawrence Radiation Laboratory. Many of the proposed peaceful applications involve underground nuclear explosions, and several experiments at the AEC Nevada Test Site have provided valuable insight into the phenomenology of such explosions. Among the possible uses currently under consideration are excav… more
Date: July 25, 1960
Creator: Lombard, David B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SHIELDING OF DEMINERALIZERS AND FILTERS IN THE HFIR PRIMARY COOLANT SYSTEM

Description: S> Thicknesses of ordinary concrete required to shield the demineralizers and filters in the HFIR primary water system were computed for normal operating conditions and for abnormal conditions such as a meltdown of the fuel within the reactor. About 4 1/2 ft, 3 1/4 ft, and 4 1/4 ft of concrete are required to shield the cation exchange unit, the anion exchange unit, and the filter unit, respectively, to the most stringent of the following radiation levels: (a) 0.75 mr/hr for normal reactor oper… more
Date: July 25, 1960
Creator: McLain, H A & Haack, L A
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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