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Heat Transfer in an Annulus with Asymmetric Heating

Description: Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
Date: February 1959
Creator: Lisin, Alexander Vladimir; Mackewicz, W. B. & Reynolds, William C., 1933-2004
Partner: UNT Libraries Government Documents Department


Description: Investigatiors were made of various materials for development of metal- canned and semi-homogeneous GCRE-II fuel element concepts. The materials were studied for application to development of fuels, grapanite, silicon-silicon carbide coatings, metal claddings, carburization barrier coatings, and graphite joining. A survey of the literature showad that uranium carbide fuels are superior to other types for the applications described and that refractory metal or metal carbide fuel coatings appear superior to other types for use with the types of graphite investigated. Experimental measurements were made of the thermal conductivity, tensile strength, stress-strain reiationships, and thermal expansion of graphite powdsr bonded with baked carbon at a final firing temperature of 760 deg C. Results showed that these materials were stronger and more isotropic at all test temperatures than a standard structure graphite such as ATJ. The thermal conductivity is somewhat lower and the thermal extansion slightly higher than the corresponding properties of ATJ. A silicon-silicon carbide coating was developed as an osidation-resistant coating for graphite. Preliminary air oxidation tests at 1000 deg C showed that the first samples survived 2000 hr with 10% failure. Subsequent experiments showed that it is reasonable to expect better performance in further tests. Tests for compatibility with graphite were conducted on zirconium, Zircaloy-2, "A" nickel, and K-Monel at 1750 and 1850 deg F for 1000 and 1500 hr. Chemical analyses, metallography, and tensile tests indicated that the K-Monel is the material most compatible with graphite; it possesses good strength and ductility with negligible carburization or carbon diffusion. Zircaloy-2 tubing showed a growth of from 3.4 to 3.8% when thermal cycled 100 times between 850 and 1850 deg F. Tests for compatibility with Hastelloy X were conducted on graphite samples coated with molybdenum, niobium carbide, and zirconium carbide at 1750 deg F and 300 psi for 1000 and ...
Date: December 30, 1960
Creator: Carpenter, R. & Del Grosso, A.
Partner: UNT Libraries Government Documents Department

RUBIDIUM AND CESIUM EVALUATION PROGRAM. SPACE POWER SYSTEMS TECHNOLOGY STUDIES. Quarterly Technical Report for Period February 1 through April 30, 1961. Report No. 1

Description: A summary is given of the development of equipment to obtain data for the corrosion and solubility properties of rubidium, and for the corrosion and thermodynamic properties of cesium. (B.O.G.)
Date: October 31, 1961
Creator: Young, P.F.
Partner: UNT Libraries Government Documents Department

SPACE POWER SYSTEMS TECHNOLOGY STUDIES. RUBIDIUM EVALUATION PROGRAM. Report No. 12. Quarterly Technical Progress Report for Period November 1, 1960 through January 31, 1961

Description: A stainless steel loop test with liquid rubidium was run for 172 hr, and the design temperature of 1510 deg F at approximately 15% vapor quality rubidium in the boiling phase was achieved. The problems of loop operation are discussed, e.g., trapped gas bubbles and argon leakage from the argon-to-water heat exchanger. The rubidium was made to boil, and its boiling point was determined to be 1325 deg F at 33 psia and 1450 deg F at 60 psia. The discrepancy between measured and literature boiling points is probably due to the fact that the thermocouples did not measure the actual rubidium temperature. The density of rubidium was measured at several temperatures from 175 to 1340 deg F and compared with literature values. (D.L.C.)
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department


Description: The corrosion and heat transfer characteristics of boiling sulfur were studied in order to evaluate the feasibility of using a boiling sulfur cycle to extract energy from a reactor. Work on the program included a literature survey of corrosion studies, capsule corrosion tests, dynamic loop corrosion tests, and boiling heat transfer experiments. (auth)
Date: December 1, 1960
Creator: Sawle, D.R.
Partner: UNT Libraries Government Documents Department


Description: The evaluation of the data generated during the full power and limited endurance tests of the ML-1 mobile nuclear power plant indicates that the reactor performs in accordance with the design specifications. During the 101 hr test period, the reactor attained a maximum power of 3.44 Mw( and 247 kw(e) was measured at the output shaft of the turbine-compressor set. No operating limits were exceeded during these tests and all systems performed satisfactorily Except for the known performance deficiency of the turbinecompressor set, which prevented the attainment of design output power, no operational, stability, or control problems were encountered. All test objectives were achieved and the tests were considered completely successful. (auth)
Date: July 1, 1963
Creator: Kattchee, N.
Partner: UNT Libraries Government Documents Department

ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. Monthly Progress Report for April 1959

Description: The Army Gas Cooled Reactor System Program includes water moderated heterogeneous reactor (Gas Cooled Reactor Experiment I), a graphite moderated homogeneous reactor (Gas Cooled Reactor Experiment II), a mobile gas cooled reactor (ML-1), and the co ordination of thc Gas Turbine Test Facility. The progress of each project, the associated tests and data evaluation, the applicabie design criteria, and the fabrication of reactor components are briefly summarized. (For preceding period see IDO-28538.) (W.D.M.)
Date: May 25, 1959
Partner: UNT Libraries Government Documents Department