This monthly document details activities of the Hanford Operations Office during the month of May 1959. (FI)

Predictions of water velocities at which fluidization and massive entrainment of filter media (sea sand, Ottawa sand, silica, and alumina) will occur in special filter beds are presented. Pressure gradients in the various fluidized beds and the maximum bed expansions expected are tabulated. (auth)

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The current status of helium and carbon dioxide technology is described in the light of the Gas Cooled Reactor Program requiremoents. The problem of containing high-pressure helium at high temperature is discussed, and it is concluded that, by proper attention to the design, construction and maintenance of a plant, a high degree of helium leak-tightness can be achieved at small additional cost when compared with a carbon dioxide system. What is more, the cost of making up helium losses in a practically achievable system is estimated to be small compared with other fixed and operating costs. Graphite-carbon dioxide reaction data are reviewed. It is shown that carbon dioxide at atmospheric pressure and low flow rates should be compatible with a graphite mooderator up to 525 C. No data are available at the high pressures and fiow rates that would be encountered in power reactors. Significantiy higher oxidation rates may result, however, perhaps limiting bulk moderator temperatures to 450 to 500 C. Improved carbon materials, protective coatings and inhibitors, and/or operating practices may be developed that will allow significant future increases in these limiting temperatures. (auth)

A list of fused-salt mixtures which are of importance in molten salt research is presented. The list is a revision and extension of the list published in ORNL CF-57-6-81. The liquidus temperatures given are believed to be within lO C of the correct values. (auth)

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The use of a scalloped cross-sectionsl coolant channel has been suggested as a possible solution of the fuel-element bowing problem inherent in the septafoil type of geometry. Using simplified assumptions, a method has been developed for calculating the red spacing and scallop size necessary to produce equal average fuel-element surface temperatures in the central and peripheral regions of the coolant flow channel at the mid-section of each fuel-red cluster under a given set of reactor flow conditions. Since the extent of rod-bowing is related to the surface temperature distribution, this requirement should minimize fuel-element deflection. ( auth) l6629 In heavy-water-cooled and -moderated power reactors such as NPD-2 and CANDU the coolant will be insulated from the moderator by a gas layer external to the pressure tubes. Therefore, these tubes must be designed to operate at the maximum coolant temperature. However, by placing the insulation inside the pressure tubes they can be kept cold; a thiner wall or a higher reactor operating temperature can be used. and a wider range of pressure tube materials be considered. Two kinds of internal insulstion are considered: the cooled pressure tube in which stagnant heavy water is the insulation, and the cooled stress tube in …

The directions for preparing the following acids from labeled acetic acid on a 1 to 20 millimole scale is presented: Succinic acid, malic acid, fumaric acid and tartaric acid. Two methods for preparing the succinic acid are detailed.

The purpose of this memorandum is to outline the high temperature hydride moderator program proposed for the.Metallurgy Division. The objectives of this program are (1) to provide physical and mechanical property data required by the reactor designers, (2) to develop methods for fabricating moderator assemblies, and (3) to devise.and conduct tests to evaluate these· assemblies. The requirements in each of these areas and the work proposed to meet them are outlined.

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Tests were conducted to determine the amount of error introduced in reactor power data by radiation-induced voltages in cables and electrometer preamplifier chassis. The results, obtained near the central exposure facility of the KEWB (Reacter Safety Experiments), showed no observable radiation effects under the conditions of present use. Cable insulation resistance was measured during the radiation bursts. (C.J.G.)

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