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Operation of the 100F pile is reported on. Ongoing construction is described; detailing population and occupancy. Visitors and the Schenectady report are discussed. A copy of the June 4 letter from Carleton Shugg to Carrol L. Wilson pertaining to flooding of the Columbia and Yakima rivers is included.

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This document serves to record pertinent information regarding detection and repair of a water leak in Process Tube No. 3169-F in the F File and subsequent steps necessary to remove the water from the pile in order to return to normal level.

This report documents the meteorological concerns for Hanford Atomic Production Operations (HAPO). There was a concern that the radionuclides that were being released in the atmosphere. The author suggests a hypothesis to keep the radionuclides from migrating in the atmosphere. This hypothesis describes the washout of radionuclides and the leaching into the soil as a method to contain the radionuclides at the production facility. The hypothesis takes into account wind velocity, stable and unstable atmospheric conditions, convection, boundary layer problems, diffusion at greater distances away from the source of pollutant, altitude, and a possible solution.

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It has been suggested in the past that special numbers of neutrons or protons in the nucleus form a particularly stable configuration.{sup1} The complete evidence for this has never been summarized, nor is it generally recognized how convincing this evidence is. That 20 neutrons or protons (Ca{sup40}) form a closed shell is predicted by the Hartree model. A number of calculations support this fact.{sup2} These considerations will not be repeated here. In this paper, the experimental facts indicating a particular stability of shells of 50 and 82 protons and of 50, 82, and 126 neutrons will be listed.

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Three individuals were inadvertently exposed to polonium. Activity determinations on the routine weekly urine samples submitted by the individuals revealed counts of 174, 734, and 2190 c/min/50 ml respectively. An investigation was immediately launched to determine the source of the exposure, since there was no report of a spill or accident involving active material. By the process of elimination, the time of exposure was narrowed down to a time when two of the individuals were engaged in the denitration of a polonium solution in a small kettie inside a hood when a leak developed in the kettle. The active solution was transferred from the kettle to a carboy. All three individuals were present during the transfer period. Two wore respirators, rubber gloves, and smocks over their coveralls while the third stood well behind and watched the procedure. However, it was concluded that an inhalation exposure resulted. A medical study of each case was instituted and data are summarized. No immediate toxic effects were observed. (C.H.)

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The major problems in this determination are the extraction of X from the sample and the isolation of the extracted X. The application of various analytical methods to these two problems indicates that the current method of analysis yields values which may be as much as 15% high. The current method of analysis is subject to positive and negative errors. The magnitude of these errors varies with techniques and with sample composition. The recommend method, although longer, is believed to be free of these errors, but a radical change, say 100 fold, in the composition of the sample would certainly require further investigation.

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A process hns been developed for impregnating graphite with U/sub 3/O/ sub 8/ in connection with the proposed use of such material for fuel rod elements in the Daniels' High Temperature Pile. The process as developed consists of five steps: Fabrication of the graphite in the desired shape; Pretreatment of the graphite by boiling in water and then firing in helium at 800 deg C; Impregnating the graphite by first evacuating the pretreated material and then admitting an aqueous uranyl nitrate solution whose concentration is etermined by the final uranium content desired in the raphite; Drying the impregnated graphite slowly under quilibrium conditions; and Conversion of the uranyl itrate to U/sub 3/O/sub 8/ by firing in helium at 800 deg C. By this process fuel rod elements have been made which contain as much as 19% U/sub 3/O/sub 8/ distributed uniformly throughout the graphite. The considerations leading to the choice of this process are discussed in this report, together with the alternate procedures which were investigated. (auth)

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The initial phase of the pressure drop testing program on proposed fuel element design shapes for the high-temperature, gas-cooled power reactor, has been completed with the compilation of pressure drop data for the flatplate riveted-assembly type of unit, the ribbed cylinder type, the single bent-plate type both with and without rivets, the 13 hexagon-6 pentagon type, and the 7-hole graphite type. This phase of the program was conducted for the purpose of determining the equivalent skin-friction pressure drop factor for composite fuel element crosssections, and for determining the joint loss factors for varying degrees of misalignment of the fuel units in the fuel channels of the pile. (auth)