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Temperature distributions in a reactor fuel plate

Description: A report pertaining to heat-transfer characteristics , the supercritical water reactor, and flat fuel plates separated by cylindrical spacers perpendicular to the plates.
Date: 1954
Creator: Long, J. K.; Chastain, Joel W.; Redmond, R. F.; Jung, R. G. & Fawcett, Sherwood L.
Partner: UNT Libraries Government Documents Department
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Boiling Potassium Heat Transfer Project Loop Design and Development

Description: This technical report reviews the general purposes and immediate goals of the Heat Transfer Group at BNL's study of the heat transfer characteristics of alkali metals with phase change in forced convective flow. This report also presents a brief description of the design and development of the test loop. Figures detailing findings accompany the report.
Date: April 30, 1962
Creator: Chen, John C., 1934-2013
Partner: UNT Libraries Government Documents Department
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Equations for Bilateral Heat Transfer to Fluids Flowing in Concentric Annuli

Description: Abstract: "Theoretical equations have been derived for calculating heat transfer coefficients for fluids flowing through concentric annuli for the following two cases: (A) constant and equal heat fluxes from both walls, and (B) constant, but unequal, heat fluxes from the walls, with equal wall temperatures at a given axial position along annular channel. In the derivations, the conditions of fully-established flow, and independence of physical properties with temperature variation across the fl… more
Date: April 10, 1962
Creator: Dwyer, Orrington Embry, 1912-
Partner: UNT Libraries Government Documents Department
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Eddy Transport in Liquid-Metal Heat Transfer

Description: This report seeks to "develop a practical method of evaluating the eddy diffusivity of heat transfer for liquid metals, so that it can be incorporated into the more or less standard theoretical methods to give heat transfer coefficients which are in reasonable agreement with experimental facts"--from introduction.
Date: February 18, 1962
Creator: Dwyer, Orrington Embry, 1912-
Partner: UNT Libraries Government Documents Department
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Thermal Test Unit

Description: Report discussing a performance evaluation of the Thermal Test Unit, a piece of test equipment fabricated to "aid the Hanford Works in experimentally determining heat transfer characteristics for a particular application."
Date: May 31, 1950
Creator: Cohen, A. & Rede, G. R.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Declassified Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, prod… more
Date: September 4, 1956
Creator: Jordan, W. H.; Cramer, S. J.; Miller, A. J. & Savelainen, A. W.
Partner: UNT Libraries Government Documents Department
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Transient Flow of Steam-Water Mixtures

Description: In the analysis of problems involving transient flow and heat transfer in steam-water mixtures, it is necessary to derive an approximate integral equation of motion for a non-ideal compressible fluid in a duct having finite discontinuities in flow geometry. This equation is derived in this document.
Date: December 12, 1955
Creator: Tippets, F. E.
Partner: UNT Libraries Government Documents Department
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Progress Report of the Reactor Science and Engineering Department; January 1 - March 31

Description: Technical report including all work on the liquid metal fuel reactor and normal water enriched uranium reactor component test projects. Includes some studies on the BNL research reactor, shielding, BrF3 extractive distillation, metallurgy, and a portion of the ultimate disposal treatment of purex wastes are included. (From Summary)
Date: 1952
Creator: Williams, Clarke
Partner: UNT Libraries Government Documents Department
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Some Considerations on the Configuration and Stability of the H2 Temperature Control Loops of the 80" Bubble Chamber

Description: There is but little known about the thermal process involving the dynamics and thermodynamics of the cycling liquid H2 in the chamber and those of the H2 fluid flow in the cooling coil as well as the geometrical characteristics of the chamber body. This the physical equations governing this process are involving so many variables that this analysis becomes rather complex even if simplifying assumptions are made. To those difficulties is added the ignorance even of an approximative expression fo… more
Date: January 7, 1964
Creator: Androulakis, John G.
Partner: UNT Libraries Government Documents Department
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A Correlation for Boiling Heat Transfer to Saturated Fluids in Convective Flow

Description: An additive mechanism of micro- and macro-convective heat transfer was formulated to represent boiling heat transfer with net vapor generation to saturated, non-metallic fluids in convective flow. The final equations are [equations not transcribed]. The second equation will be recognized as the Dittus-Boelter equation with the additional factor F. The two functions F and S are defined as [equations not transcribed] where Re is the effective Reynolds number for the two-phase fluid and ΔTe is the… more
Date: December 26, 1962
Creator: Chen, John C.
Partner: UNT Libraries Government Documents Department
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On the Transfer of Heat to Fluids Flowing Through Pipes, Annuli, and Parallel Plates

Description: Nusselt numbers have been calculated for heat transfer to fluids flowing through annuli under conditions of uniform heat flux and fully established velocity and temperature profiles. The following cases were considered: (a) laminar flow, (b) slug flow, (c) turbulent flow with molecular conduction only, and (d) turbulent flow with both molecular and eddy conduction. These Nusselt numbers were determined for two conditions: heat transfer from the inner wall only and heat transfer from the outer w… more
Date: January 8, 1963
Creator: Dwyer, O. E.
Partner: UNT Libraries Government Documents Department
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Heat Transfer Study for Self-Boiling Radioactive Wastes

Description: The temperature characteristics associated with the handling of self-boiling radioactive wastes from the separations extraction processes in the Chemical Processing Department have necessitated several heat transfer studies. Earlier studies 1,2,3 defined the feasibility of self-concentration in existing waste storage facilities by determining the rate of heat generation from the decay of stored fission products and by defining the rate of heat loss from existing storage tanks to the surrounding… more
Date: April 27, 1959
Creator: Stivers, H.W. & Taylor, H.W.
Partner: UNT Libraries Government Documents Department
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A Proposed Mechanism and Method of Correlation for Convective Boiling Heat Transfer with Liquid Metals

Description: An additive, interacting mechanism of micro and macro-convective heat transfer is proposed to represent boiling heat transfer with net vapor generation to saturated liquid metals in convective flow. Based on this mechanism, a method for calculating boiling coefficients is developed. The correlating is shown to be in fair agreement with early experimental results for convective boiling of potassium and sodium.
Date: October 14, 1963
Creator: Chen, John C.
Partner: UNT Libraries Government Documents Department
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The Application of Inert Fluidized Beds to the Volatility Reprocessing of Reactor Fuels

Description: In the reprocessing of spent solid fuels from nuclear reactors by direct volatilization, one of the major problems is the removal of heat from the highly exothermic gas-solid reactions. The use of fluidized beds of inert granular material as heat transfer media to control these exothermic reactions forms the basis of one approach to volatile reprocessing which is under development at BNL The engineering scale work carried out under this development program is discussed.
Date: 1961
Creator: Regan, W. H.; Reilly, J. J.; Wirsing, E. & Hatch, L. P.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Secret Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, prod… more
Date: September 4, 1956
Creator: Jordan, W. H.; Cromer, S. J.; Miller, A. J. & Savelainen, A. W.
Partner: UNT Libraries Government Documents Department
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Heat Transfer in Radiant- Heat Spray Calcination

Description: The fixation of aqueous radioactive wastes in a stable solid media by means of calcination has been the subject of considerable research and development effort. Several methods of doing this on a continuous basis have been devised and a few have been demonstrated to be feasible for the handling of non-radioactive or low activity simulated wastes. Currently an investigation of calcination by means of radiant-heat spray drying is being carried on by the Chemical Research Operation of the Hanford … more
Date: February 1, 1959
Creator: Johnson, B.M., Jr.
Partner: UNT Libraries Government Documents Department
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Heat Transfer Testing

Description: Several tests are being performed and others being planned to investigate the role of heat transfer in corrosion processes. These tests are measuring both corrosion rates of metals (Zr-2 and X-8001 aluminum) under heat transfer, and the temperature rise associated with the buildup of the corrosion product. A brief description of these tests is given in this report.
Date: July 7, 1959
Creator: Doman, D. R.; Hokenson, J.F. & Lobsinger, R. J.
Partner: UNT Libraries Government Documents Department
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A Study of the Effects of Some Spray Column Variables on Radiant-Heat Transfer in Spray Calcination

Description: Calcination of liquid radioactive wastes, the process of converting metal nitrates and sulfates to oxides by heat, is under development at Hanford as a means of reducing these liquids to a dry powder or solid which can be stored safely. Radiant-heat spray calcination, one of the methods under study, was first investigated at the Oak Ridge K-25 Plant (1) as a possible method of calcining uranyl nitrate to uranium trioxide. The process has also been under extensive development at the Pulp and Pap… more
Date: April 28, 1960
Creator: Allemann, Rudolph Theodore
Partner: UNT Libraries Government Documents Department
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Heat Transfer Rates for Cross-flow of Water Through a Tube Bank at Reynolds Numbers up to a Million: Part II. Circumferential Variation of Film Coefficient for Individual Tubes.

Description: The tube bank used in this study consisted of 200 tubes, 10 wide and 20 deep. They were made of nickel, had an outside diameter and thickness of 0.810 and 0.063 inches, respectively, and were spaced on equilateral triangular corners, 1.28 inches apart. The purpose of the work was to determine the circumferential, or angular, variation of the film coefficient for individual tubes at various locations in the tube bank, with water flowing at 360°F and Reynolds numbers in the range 28,000 to 1,200,… more
Date: unknown
Creator: Dwyer, O. E.; Shechan, T. V. & Weisman, Joel
Partner: UNT Libraries Government Documents Department
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Trip Report Consultation on Organic Reactor Coolants

Description: There is a continuing high interest in the development of organic coolant technology for application to future Hanford reactors. In addition to the HAPO organic program, two other programs are being sponsored by the Atomic Energy Commission. These include the Naval Reactor program, aimed at a reactor for ship propulsion, and the Civilian Power Reactor program. Because of the similarity of the technical efforts in the three programs, an attempt is being made to establish effective liaison among … more
Date: November 5, 1956
Creator: Atwood, J. M.; Cook, M. W. & Eddy, P. P
Partner: UNT Libraries Government Documents Department
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