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in subjects: "Liquid Metals"  
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Request for Nuclear-Ramjet Radiator Weight Data

Description: Weight data on the following liquid metal to air radiators is requested. This information is to be used in a comparison of the performance attainable with different nuclear reactors and liquid metal systems in a ram-jet powered airplane. The radiator dimensions are based on estimates using the performance curves presented in CNLM-338.
Date: June 23, 1958
Creator: Larson, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Depletion of Minor Constituents From Coast Metals No. 52 (89 Ni-5 Si-4 B-2 Fe) and No. 53 Metals No. 52 (89 Ni-8 Cr-4 B-4 Si-3 Fe) Brazing Alloys During Various Exposures

Description: Corrosion tests were made on nickel-base brazing alloys containing boron snd silicon in fused fluoride fuels, liquid metals, nnd oxidizing atmospheres. Impoverished regions, after the tests, contained, approximately one third the original amount of boron and silicon that was present before the tests. (A.C.)
Date: October 23, 1958
Creator: Jansen, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE THERMAL CONDUCTIVITY OF A MOLTEN Pu-Fe EUTECTIC (9.5 a/3 Fe)

Description: The thermal couductivity of the Pu-- Fe eutectic mixture (9.5 at.% Fe) was measured in both the solid and liquid states by the use of a guarded cylinder apparatus which operated in a high vacuum. The apparatus was designed as an absolute measuring devlce and was checked with a known material. The thermal conductivity values obtained varled from 0.034 at 220 C to 0.0412 at 400 C in the solid state and from 0.045 at 420 C to 0.045 at 520 C in the molten state, with the units of cm sec C. The curv… more
Date: July 1, 1958
Creator: Deverall, J.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pyrometallurgical Purification of Plutonium Reactor Fuels

Description: Pyrometallurgical methods studied are liquation, self-drossing and filtration, slagging by the addition of oxide, carbide, or halide, liquid metal extraction, complete conversion to halide, followed by filtration and selective reduction of the plutonium, and electrorefininng. Experimental techniques and results are presented for each method. (auth)
Date: June 1, 1958
Creator: Leary, J.A.; Benz, R.; Bowersox, D.F.; Bjorklund, C.W.; Johnson, K.W.R.; Maraman, W.J. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Status Report in Eddy Current Theory and Application

Description: New developments and improvements in non-destructive testing techniques by means of eddy currents are presented. The applications include impedance of a coil near a conductor minimizing the effect of probe-to-metal spacing, pulsed eddy current system for gaging plating thickness and for testing liquid metal bonding, multifrequency eddy current testing system, testing instrument for the determination of wire quality with an application to the spacing wires, and an application to the measurement … more
Date: November 1, 1958
Creator: Renken, C.J.; Myers, R.G. & McGonnagle, W.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Engineering Department Progress Report for May 1-September 30, 1957

Description: Thermal neutron diffusion lengths in bismuth were measured, and measurements on bismuth--graphite lattices were started. Uranium--fased salt phase and distribution studies were continued. A standard cell was designed for determining solute concentrations in fused chloride mixtures and liquid bismuth solutions. Absorption spectroscopy shows promise as a method for determining the concentration of uranium in fused chloride mixtures. Both theoretical and experimental studies were made of xenon rem… more
Date: October 31, 1958
Creator: Maslan, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermodynamics and Phase Relationships for Plutonium Oxides

Description: A compilation of available fundamental information concerning plutonium oxides. Methods of preparation, thermodynamic data, phase relationships, crystal structures, and some information on mixed oxide systems are considered. A bibliography is included. Methods of preparing PuO/sup 2/ by the peroxide and the oxalate processes and of lower oxides by thc reduction of PuO/sub 2/ are described and some chemical properties of plutonium oxides of interest in processing certain fuel elements are given.… more
Date: October 31, 1958
Creator: Holley, C.E. Jr.; Mulford, R.N.R.f Huber, E.J. Jr.; Head, E.L.; Ellinger, F.H. & Bjorklund, C.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRELIMINARY REPORT OF FUSED SALT MIXTURE NO. 130 HEAT TRANSFER COEFFICIENT TEST

Description: Heat transfer data are presented over a Reyuolds Number range of 400 to 8000 for the test fused salt Mixture No. 130 (62 mol % LiF-37 mol % BeFi-1 mol % UF/sub 4/ for a calibrating used salt Mixture No. 30 (50 mol % NaF--46 mol % ZrF/ sub 4/--4 mol % UF/sub 4/) flowing inside round heat exchanger tubes. A prelima- nary equation is developed for predicting shell-side heat transfer coefficients for liquid metal in turbulent, longitudinal flow over a square tube array having a pitch/diameter ratio… more
Date: April 1, 1958
Creator: Amos, J.C.; MacPherson, R.E. & Senn, R.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lithium Symposium--Analytical Procedures and High-Temperature Corrosion. Reading List

Description: ABS>A list of 222 references pertaining to corrosion by molten Li and related subjects was compiled in connection with a Lithium Symposium held at the Oak Ridge National Laboratory on August 7-8, 1957. This list is by no means exhaustive but it is thought to contain most of the information presently available on these subfects. In many cases the individual references will contain additional references. (auth)
Date: January 20, 1958
Creator: Hoffman, E. E. & Jansen, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PROPOSAL FOR AN EXPERIMENTAL STUDY OF THERMAL GRADIENT MASS TRANSFER IN A THERMAL CONVECTION LOOP

Description: S>A proposal is presented to design, construct, and operate a thermal gradient mass transfer loop to provide data on rates of solution and deposition as functions of time. Operation of the hot solution zone under controlled isothermal conditions is planned. It is felt that data obtained in such a loop would be of value in assessing the validity of presently proposed mecharisms for thermal gradient transfer or in devising new ones. The thermal and forced convection loops appear to offer moat pro… more
Date: February 18, 1958
Creator: Prados, J.W. & Scott, J.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion and Creep Behavior of Tantalum in Flowing Sodium

Description: The corrosion behavior of commercial tantalum in high-purity flowing sodium from 700 to 1200 deg F and the effect of sodium exposure on the creep strength of tantalum at 1200 deg F were investigated. The tests were conducted in forced-convection flow loops constructed of Type 315 stainless steel. With continuously gettered sodium systems (probably containing less than 10 ppm oxygen) operating for periods up to 50 days, weight losses sustained by 1200 deg F specimens corresponded to only about 0… more
Date: August 21, 1958
Creator: Raines, G. E.; Weaver, C. V. & Stang, J. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JULY, AUGUST, SEPTEMBER 1958

Description: 8 2 5 6 7 6 1 1 B 3 7 3 7 reprocessing scheme which may be applicable to most power reactor fuels is described. The irradiated fuel is dissolved in an appropriate aqueous solution which is then calcined to a mixture of dry oxide. Fluorination of the mixture ultimately produces the hexafiuorides of U and Pu, which are volatilized. This process will be called the ADF (aqueous dissolution and fluorination) process. The fluorination rates of UF/sub 4/ and PuF/sub 4/ were investigated. Since oxides,… more
Date: December 1, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Study of the Liquidus in Aluminum-Uranium Alloys

Description: Liquidus temperatures in the aluminum -uranium system have been redetermined for alloys containing 13 to 50 wt. % uranium. Thermal analysis, electricalresistance measurements, and metallography were employed in the investigation. The binary aluminumuranium alloys studied and, their corresponding liquidus temperatures are as follows: 17 wt. % uranium, 755 deg C; 17.5 wt. % uranium, 780 deg C; 24.5 wt. % uranium, 954 deg C; 30.9 wt. % uranium, 1068 deg C; 41.6 wt. % uranium, 1190 deg C; 51.2 wt. … more
Date: May 1, 1958
Creator: Storhok, V. W.; Bauer, A. A. & Dickerson, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During October 1958

Description: Thermal-conductivity and electrical-resistivity measurements were made on U-1.5 wt,% Zr, encapsulated in Zircaloy-2 with a NaK thermal bond. Data are presented on thermal conductivity measurements made on UO/sub2/ specimens. A method of sink-float measurement to identify factors affecting irradiation- induced volume changes in graphite was continued. The stress-rupture and creep properties of 15% cold-worked Zircaloy-2 are being investigated in the 290 to 400 deg C temperature range in vacuum. … more
Date: November 1, 1958
Creator: Dayton, R. W. & Tipton, C. R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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