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Project C-431-A includes the design of the C Water Plant outfall structure. This report documents design assumptions and the design of the spillway, outfall sewers, spillway chute, trash racks, walkways, stop log and trash rack slots, main sewer, and retention sewers. The spillway capacity is to be 268,000 gpm with a crest elevation at 429.0. This flow capacity is composed of flow from the 105-C Retention Basin (80,000 gpm), 105-B Retention Basin (45,000 gpm), and the 190-C Area main sewer (143,000 gpm).

This is a progress report of the production on the Hanford Reservation for the month of June 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

The study of radiation damage to the graphite moderator is largely dependent upon the availability of graphite samples from the moderator itself. Because of the varied temperature-flux history and complicated structure of the piles, it is impossible to study the problem from the laboratory standpoint alone. The samples of greatest interest are those taken from the sections of the moderator which have received the greatest damage. However, a comprehensive study requires samples from all sections of the graphite moderator. It is desirable that these samples be solid in order that physical and dimensional measurements of all types may be made. Solid samples enable thermal conductivity measurements and the gradients of damage across tube blocks to be measured. To provide such samples, it was necessary to design some device which would cut solid samples from any location in the pile through the process Channels. The graphite core borer was desigred specifically for this purpose. The objective of this Production Test was to test the operation of the core barer and evaluate the results of its performance.

Two important problems in the investigation of reactor hazards are the chemical reactivity of various materials employed in reactor construction and the chracteristics of heat transfer under transient conditions, specifically heat transfer when driven by an exponentially increasing heat source (exp t/T). Although these problems are independent of each other, when studied in relation to reactor hazards they may occur in a closely coupled sequence. For example the onset of a dangerous chemical reactor may be due to structural failure of various reactor components under an exponentially rising heat source originating with a runaway nuclear reactor. For this reason, these two problems should eventually be studied together after an exploratory experimental survey has been made in which they are considered separately.

A correlation of spontaneous fission rates with Z and A is made to show that these rates depend on the nuclear type. Some suggestions as to the mechanisms are given and it is also shown how these relate to the mechanism of slow neutron and photo fission.

Resting cells of eleven microorganisms were exposed to radioactive carbon dioxide for 40 minutes. The radioactive compounds formed during this time were separated and identified by paper chromatography. Resting cells of Lactobacillus casei fixed no carbon dioxide and growing cells fixed carbon dioxide primarily in malic and aspartic acids. All of the radioactive compounds formed could have become radioactive by reversal of known decarboxylation reactions.

The operating holdup and flooding rates of uranium hexafluoride, n-heptane, and perfluorodimethylcyclohexane have been studied in a glass still filled with 1/8 inch nickel Heli-Pak. The flooding rates of the latter two substances are 46.0 and 48.0 cc./min. respectively and the flooding rate for uranium hexafluoride, calculated from the Bertetti equation, is 42.9 cc./min. The operating holdups for these three substances on Heli-Pak were measured at several throughput rates up to the flooding rate and an equation derived, based on the method of Jesser and Elgin, for computing the holdup of uranium hexafluoride from a knowledge of the holdup of perfluorodimethylcyclohexane. Observations of the performance of the packing and a measurement of the number of drops of uranium hexafluoride per milliliter at 75 deg C. are also presented.

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The volume of H/sub 2/ evolved on dissolving screened nonroasted U- bearing scrap, slag, and liner in HCl were determined; the values were found to indicate the degree of removal of metallic particles by screening. Digestions of nonroasted plant-pulverized scrap with HNO/sub 3/, NaNO/sub 3/, or Fe/sub 2/(SO/ sub 4/)/sub 3/ in HCl and with HNO/sub 3/ or NaNO/sub 3/ in H/su b 2/SO/sub 4/ were not so effective as digestion with NaClO/sub 3/ in HCl. Doubling the free acid content and addition of FeSO/sub 4/ improved the efficiency of the latter digestion. Removal of CaF/sub 2/ from crude (NH/sub 4/)/sub 2/ UO/sub 4/ by solution of the uranate in acetic acid, HCl, or Hsub 2SO/sub 4/ was limited by slow filtration rates. (W.L.H.)

A consideration of the characteristics of fused salt-- ThF/sub 4/ solutions suitable for use in homogeneous reactors is presented, together with a brief survey of the literature pertaining to such solutions and a summary of the experimental work accomplished. (auth)

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Document HW-21096, inquires regarding changes in equipment, so that various proposed flows of process water to each of the present production units, at several 105 control room pressures, may be effected. The proposed conditions are shown in table form in the report. For the purpose of calculations upon which this letter is based, the pressure used here is that which is recorded at the 105 control room ``inlet`` panel. It is actually the top of riser pressure, plus static head between the recorder and the point of pressure tap.