Research and development activities are reported on Borax V, ZPR- III, - VI, and -IX, EBR-I, EBR- II, and FARET. Reactor technology investigations are reported in reactor physics, reactor fuel development, viewing systems, heat engineering, and chemical separations. Research on advanced systems is reported on reactors and undersea nuclear power applications. Nuclear safety development in thermal and fast reactors is also reported. (J.R.D.)

Fabrication of the components for the FDM-1 converter and its back-up device was completed. The FDM-1 converter was assembled, and preparations for testing were completed. Performance testing was initiated, and a total of 330 hours of operation above 1000 deg K in a cesium environment were logged. The peak emitter temperature reached was 2000 deg K with a thermionic output of nearly 2 watts/cm/sup 2/. Indications of a cesium leak were observed, and the device was shut down for examination. A 500-hour thermal endurance test of the clad fuel pellets was performed. A post-test examination was conducted, and no diffusion of UO/sub 2/ into the cladding was observed. A thermal conductivity test specimen was exposed to a temperature of 1550 deg C for 500 hours with the result that some intergranular diffusion was noted. The post-test examination of the vacuum emission test pellet was also completed. The design of the advanced double-diode thermionic converter utilizing the results of prior efforts was initiated. (auth)

References to 529 articles on nuclear reactor control, kinetics, and stability published before autumn 1962 are included. Emphasis is on calculations and theory since the references serve as an aid in analyzing the dynamic behavior of SNAP reactor systems. (D.C.W.)

This is the monthly report for the Hanford Laboratories Operation, July 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This document discusses the leak repair of the 107-D retention basin. Leakage of effluent water from the 107-D Basin had increased from 6000 gallons per minute in November of 1959 to the peak of 8000 gallons per minute in April of 1963. Washout of fines had apparently created large voids beneath the north and west walls and endangered the integrity of the structure by settling the wall 2 in. at one place. The leakage was arrested in March of 1963 by filling the voids with concrete and grout and sealing the repairs with a newly developed sealant. Present total leakage is 3750 gallons per minute.

This is the monthly report for the Hanford Laboratories Operation, October 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

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This is the monthly report for the Hanford Laboratories Operation, December 1962. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This document details activities of the irradiation processing department during the month of January, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

This document details activities of the irradiation processing department during the month of October, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

This is the monthly report for the Hanford Laboratories Operation, September 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

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An engineering study was recently performed by Separations Process Design Engineering to determine the feasibility of processing the total Chemical Processing Department production load in the Purex Plant. This document summarizes the results of the study and the basis for the scope design or the multipurpose dissolvers for the Purex Plant.

A milking method was developed for the production of the short-lived Al/ sup 28/ for use in physiological experiments. A Mg/sup 28/ solution is obtained by the irradiation and purification of a Li/sup 6/Mg/sup 26/ alloy, and it is placed on a Dowex 50W column in the Na/sup +/ form and then washed with 1 N NaOH. The Al/sup 28/ is eluted in 10 to 30 sec by 1 N NaOH solution containing 0.5 mg/ ml of carrier Al. The half lives of Mg/sup 28/ and Al/sup 28/ were determined to be 20.88 plus or minus 0.06 hr and 2.238 plus or minus 0.006 min, respectively. (D.L.C.)

The design and performance of SRE Core II fuel elements, moderator cans, hot traps, cold traps, control elements, pumps, main primary heat exchanger, valves and sodium piping, and instrumentation are discussed. (R.E.U.)

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

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The conversion of strontium-90 to strontium titanate heat source pellets is described. Encapsulation of the fuel in Hastelloy C containers and necessary leak testing, decontamination and calorimetry procedures are covered. Loading of the SNAP 7B thermoelectric generator was accomplished. (auth)

Additional measurements were made of steam-void fraction, temperatures, and pressures in the KEWB capsule experiment. Analysis of data indicated that friction in the volume transducer piston was large during most of the transients. The dynamic piston friction was reduced to negligible magnitudes. A method for calculating the transient heat flux from the fuel disc was formulated. Boiling stability experiments were begun with a 2-ft-long rod bundle, consisting of a square array of 18 stainless-steel rods 0.25-in. dia, spaced on 0.312-in. centers. The rods are electrically heated in a natural-circulation loop, at one atmosphere pressure. A survey was began on theories and data on hydrodynamic instabilities in natural-circulation boiling systems. Preparation of apparatus for measurement of flow-void transfer functions in a SPERT IA channel was essentially completed. (M.C.G.)

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Pressure oscillations imposed upon a compressible fluid flowing in a duct produce a substandtial increase of heat transfer between the heated duct wall and the fluid. An experimental investigation was made of the causes of this increase. Resonant conditions in a duct were used to achieve increased oscillating amplitudes. The local heat transfer incresse was found to be highly dependent on the amplitude of the local velocity oscillations, and to depend also on the frequency of oscillations and the duct steadystate pressure and Mach number. The presence of flow reversal further increased the observed heat transfer.

The operations in a process proposed for recovering uranium from spent uranium-- zirconium alloy fuels, including collecting the volatilized chlorination products (mainiy zirconium tetrachioride and uranium pentachloride) in boiling water, concentrating the resulting solution, lowering the freezing point by removing chloride with hydrogen peroxide, and recovering uranium from the 5 M Zr product solution by solvent extraction with tributyl phosphate in Amsco diluent, were investigated in the laboratory and appeared to be reducible to large-scale practice. The high temperature chlorination equipment would also be adaptable for burning graphite matrix fuels and when combined with Darex equipment for processing fuels containing stainless steel, molybdenum, or aluminum may provide the basis for a feasible universal fuel processing system. (auth)

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Development progress is reported on fast reactors, liquid metal cooled reactors, ZPR-III, ZPR-VI, ZPR-IX, Borax-V, Faret, EBR-I, EBR-II, Treat, Fermi Fast Breeder Reactor, critical assemblies, Argonne Fast Source Reactor, EBWR, Argonne Advanced Research Reactor, magnetohydrodynamic cells, fuel cells, and boiling water reactors. Reactor technology is reported on fuel development and properties, physics, heat engineering, materials development, chemical separations, nuclear safety, and nondestructive testing. (N.W.R.)