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Subcontract Work by Thompson Products, Inc.

Description: In April, 1954, Thompson Products Inc. formally began work on a program leading to the fabrication of two test radiators. The work done to date is summarized in report number PWAC-127, First Technical Report by Thompson Products Inc. on Liquid-Metal-to-Air Radiators and in PWAC-128, Second Technical Report by Thompson Products Inc. on Liquid-Metal-to-Air Radiators. The first report describes possible radiator design concepts meeting the required specifications and presents an analytical method which was derived to optimize the designs. Thompson Products has decided that a core with cast NaK passages in combination with the sheet-metal, ribbon fins on the airside offers maximum reliability. The second report formulates the analysis of the final radiator design and presents the fabrication and evaluation studies used to select the design. To evaluate the permeability of cast NaK passages, Thompson Products is planning to build a hot NaK flow rig. A parallel investigation on wrought materials will be carried out as an alternate NaK passage type. The next phase of the program, the final design of the test radiator, has started.
Date: April 20, 1955
Creator: Shaw, R.H.
Partner: UNT Libraries Government Documents Department

Correlation of Cavitation Inception Data for a Centrifugal Pump Operating in Water and in Sodium Potassium Alloy (NaK)

Description: For the centrifugal pump under investigation, the static head at pump suction, in feet absolute, at cavitation inception was correlated for water and for 1500 F NaK on the basis of the differences of the vapor pressures of the two liquids. The difference between the vapor pressure of water and NaK, for the same conditions of pump speed and liquid flow, was added to the water-test cavitation inception value, and this estimate proved to be a good approximation to the experimental value found for cavitation inception with NaK. (auth)
Date: December 11, 1958
Creator: Grindell, A. G.
Partner: UNT Libraries Government Documents Department

EFFECT OF SPACER DENSITY ON HEAT TRANSFER AND PRESSURE DROP IN THE ART FUEL- TO-NaK HEAT EXCHANGER

Description: Heat transfer and isothermal friction characteristics of the experimental ART fuel-to-NaK heat exchanger have been determined for three degrees of spacer density. The data appear to indicate that for a given heat exchanger pressure drop, the heat transfer cocfficient is almost independent of the spacer density; as the spacer density is decreased, the Reynolds modulus increases to such an extent that the Nusselt modulus does not change significantly. For a given available pressure drop, with decreased spacer density, a larger flow rate exists allowing the same heat removal rate with a lower axial temperature change or a greater heat removal rate with the same axial temperature change. (auth)
Date: October 10, 1956
Creator: Wantland, J.K.
Partner: UNT Libraries Government Documents Department

DESIGN FEATURES OF CAPSULES FOR HIGH-TEMPERATURE IRRADIATIONS

Description: An analysis was made of the problems of control and measuremeat of specimen temperature and heat generation in a NaK-filled capsule containing a fuel specimen. A specific problem is used in this report to demonstrate the large uncertainties normally encountered even in capsules containing thermocouples. This analysis indicates that an improvement by a factor of more than three (i.e., from an uncertainty of plus or minus 7O F to plus or minus 2O F in the example used) may be obtained by use of a differential- thermocouple heatflow meter and by use of a precision thermocoupleplacement clip. Since the irradiation damage suffered by fuel specimens is sensitive to small changes in temperature and burnup, improvements in precision in irradiation testing are of great importance in fuel studies. If the indicated improvement of precision by a factor of three is actually obtained when capsules of this design are irradiated, the experimenter will be able to draw much more reliable conclusions from a given testing program. (auth)
Date: September 22, 1958
Creator: Stang, J.H.; Goldthwaite, W.H. & Dunnington, B.W.
Partner: UNT Libraries Government Documents Department

Survey of Sodium Pump Technology

Description: A review is presented of the current status of sodium pump development as related to nuclear power applications. A description is given of the design features and performance characteristics of the more important types of sodium and sodium-- potassium alloy (NaK) pumps. Some requirements for sodium pumps for future large liquid metal reactor systems are presented with some preliminary consideration of the potential of various pump types to meet these requirements. (auth)
Date: June 1, 1963
Creator: Nixon, D. R.
Partner: UNT Libraries Government Documents Department

Transverse Pressure Difference Across Staggered and Inclined Spacers in the Art Fuel-to-NaK Heat Exchanger

Description: The ART fuel-to-NaK heat exchanger was modified with six 60 staggered spacers and six 60 inclined spacers alterately placed. Transverse pressure taps were installed across one spacer of each type. The average transverse pressure difference across each instrumented spacer was expressed in terms of the ratio of the transverse pressure difference to the quantity, pu/sup 2//2g,, over the Reynolds modulus range of 3,000 to 8,O00. For the inclined spacer, this term fell between 1.4 and 1.1; for the staggered spacer, the data varied randomly between 0.01 and 0.3 with no definite trend established. The tube bundle friction factor was also determined and fell about 10% below the data previously obtained using vertical spacers. (auth)
Date: June 29, 1956
Creator: Wantland, J. L.
Partner: UNT Libraries Government Documents Department

EXAMINATION OF ORNL 1 AND 2 INTERMEDIATE HEAT EXCHANGERS, TYPE IHE-3

Description: Failure, which resulted in the stoppage of fluoride flow in ORNL No. 1, occurred as a NaK to fuel leak in the vicinity of the NaK inlet heater. The reaction of NaK with fuel at this point caused the deposition of nearly pure UF/ sub 3/ around the tubes and, finally, a sufficient increase in the melting point of the fuel to produce solidification. Fluorides throughout the heat exchangers were found to be depleted in uranium and to contain some potassium. Thus it would appear that stoppage of flow occurred after considerable NaK pick-up had taken place. Fluoride attack observed in these heat exchangers, with the exception of the area of failure, agreed substantially with what would be predicted from other dynamic systems. However, in those tubes near the point of failure, attack on the"tension" side of the tubes occurred to depths approximately twice those observed in "unstressed" tubes at comparable temperatures. Mass transferred particles were present in the NaK circuit of ORNL No. 1 to a maximum thickness of 15 mils. Deposit thicknesses varied markedly from header to header. (auth)
Date: July 20, 1956
Creator: DeVan, J H & Crouse, R S
Partner: UNT Libraries Government Documents Department

A Survey of the Hazards Involved in Processing Liquid Metal Bonded Fuels

Description: A survey of the character and magnitude of hazards involved in processing liquid metal bonded fuels was made and the scope of a preliminary experimental program outlined. Processing of SRE and CPPD fuels by mechanical decladding followed by controlled reaction of the collected methods. Simdlarly, shearing of PRDC fuel and controlled exposure of the Na in the severed portions to water appears more desfrable than chethical dissolution of the metallic cladding. (auth)
Date: August 14, 1961
Creator: Adams, J. B.
Partner: UNT Libraries Government Documents Department

CORROSION OF PLUTONIUM ALLOYS IN NaK

Description: A Pu-Al alloy containing 4 at. % Ad showed no attack after exposure to purified NaK for one month at 400 deg C in the absence of any oxide. The same specimen and other Pu alloys, including pure Pu, showed marked deterioration in shorter exposures in the presence of oxide fllms from a welded stainless steel container. Pure U was found to be resistant in the presence of such oxides. (auth)
Date: July 1, 1953
Creator: Hyman, H.H. & Katz, J.J.
Partner: UNT Libraries Government Documents Department

SUMMARY OF INVESTIGATIONS UPON THE UO$sub 2$-NaK SLURRY AS A POTENTIAL REACTOR FUEL

Description: A summary is given of studies carried out with the UO/sub 2/-- NaK slurry system to ascertain its potential properties as a fuel for advanced reactor system. Included are the studies of the physical-chemical properties of the slurry, the early loop investigations, in-pile studies, and the exploration of the engineering system behavior of the material. The work was carried out in three different institutions. The Argonne Nattonal Laboratory was responsible for the early loop studies and the in-pile work, as well as some phases of the physicochemical behavior. The engineering studies were carnied out for ANL by the Mine Safety Appliances Corporation, Callery, Pennsylvania, The physicochemical studies were performed by the Armour Research Foundation, Chicago, Illinois. The studies under the program were relatively modest, but they did serve to demonstrate some of the attractive properties of the material as well as its limitations. Specifically, the dropout behavior was demonstrated in piping a tank systems in both conventional and specially designed systems, Hydraulic characteristics were demonstrated, and it was observed that a 10 vol% slurry was the maximum concentration that could convenientiy be handle in conventional engineering systems. In-pile performanc of the slurry was demonstrated and it was concluded that slurries do have potential for application in specialized, advanced systems. (auth)
Date: November 1, 1962
Creator: Carlson, R.D. & Sowa, E.S.
Partner: UNT Libraries Government Documents Department

METALLOGRAPHIC EXAMINATION OF ORNL NO. 1, SHE NO. 2

Description: Small Heat Exchanger ORNL No. I, type SHE No. 2, was removed from test stand B after 2071 hours of operation; 1041 hours were under 4 T conditions. The heat exchanger contatned 20 Inconel tubes having an outside diameter of 0.25 in. and a wall thickness of 0.025 in. The outside of these tubes was exposed to the fluoride mixture NaF contained NaK (44% Na--56% K). During o degradation t T conditions, the fluoride temperature entering the heat exchanger was 1310 tained F and on leaving was 1235 tained F. The temperature of the NaK entering the heat exchanger was 1050 tained F and at the exit was 1290 tained F. During isothermal operation, the temperature of both the NaK and fluoride circuits was 1300 tained F. Thirtysix termperature transitions from isothermal to o degradation t T conditions were made during the course of operation. An examination of the resistance heater used in conjunction with this heat exchanger also was made: the results are reported. (auth)
Date: February 1, 1957
Creator: VanCleve, J.E.; DeVan, J.H. & Crouse, R.S.
Partner: UNT Libraries Government Documents Department