This is the monthly report for the Hanford Laboratories Operation, April, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities. Biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation programming, radiation protection, and laboratory auxiliaries operation are discussed.

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Fission products, which may leak from the fuel and activated corrosion products from stainless steel surfaces, influence the design of several systems which support the main coolant system. Since the radioactivity in the main coolant resulting from these impurities must be limited to reasonable levels during operation, a purification system becomes important. Air conditioning of the vapor container as a result of possible main coolant leakage may be necessary during and after operation to remove airborne activity. After shutdown, treatment and disposal of active effluents becomes the function of a waste disposal system. Activities are tabulated, by individual isotopes, for 10,000 hours of full power operation. (auth)

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Chemical control of the SM-2 was evaluated both as a partial substitute for burnable poison in the fuel element meat and as a means of improving plant performance. Based on a review of existing information, boric acid was chosen as the reference soluble poison. It was shown that 60% of the burnable B/sup 10/ in the fuel element matrix could be replaced by soluble B/sup 10/ in the coolant without impairing plant stability during load transients. The feasibility of improving power distribution and reducing the number of control rods by supplementing the burnable poison with chemical control was also demonstrated. A preliminary design of an injection and removal system was prepared for the SM-2. (auth)

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The compound RbU/sub 6/F/sub 25/ has a hexagonal crystal structure with the parameters a/sub o/ = 8.195 plus or minus 0.002 A and c/sub o/ = 16.437 plus or minus 0.002 A. This compound is believed to be isomorphous to KU/sub 6/F/sub 25/ and KTh/sub 6/F/sub 25/. (auth) uranium hexafluoride -chlorine trifluoride -hydrogen fluoride from a knowledge of the behavior of the three binary systems. The conditions under which chlorine trifluoride and hydrogen fluoride could be removed from uranium hexafluoride by fractional distillation are discussed. (auth)

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The hazards associnted with the use of magnesium capsules in a CO/sub 2/- cooled reactor system have been analyzed, and consideration has been given to incidents which could lead to excessive temperature excursions and factors which could significantly reduce the ignition temperature of magnesium alloys. Methods of reducing the hazards associated with the Calder Hall type of reactor are discussed, and an experimental approach with which to define more aaccurately conditions that would lead to ignition is suggested. (auth)

An estimate is presented which is intended to establish an expected order of magnitude of resulting thermal neutron-induced activity and relative production of stable and radioactive isotopes in soil. The estimate is based on a one MT weapon (100%) fusion detonated at the surface of Nevada Test Site soil. (W.D.M.)

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The objective of this project was to remove impurities in the form of PbO/sub 2/ from a HNO/sub 3/ solution by electrolysis. This electrolytic cell must process up to a 15-gal. batch in a minimum of time. It is desirable that the impurity remaining after processing be less than 20 ppm. Construction and operation of the cell are described. (G.Y.)

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Information concerning diffusion is presented, including a study of the relative rates of diffusion of Fe/sup 55/ and Fe/sup 59/ in Ag, diffusion of Ru in Ag, self-diffusion in AgCd and AgIn. chemical and tracer diffusion in Ag-alpha AgCd diffusion couples, the influence of pressure on diffusion in AgZn alloys, the energy of motion of vacancies in Au at high pressure, and ionic conductivity of alkali halides as a function of pressure and temperature. A list of publications containing diffusion information is also included. (J.R.D.)

About twenty-five to thirty per cent of the uranium slugs canned in the Metal Preparation Section do not meet specifications and are rejected. These rejected slugs are recovered by a chemical process and prepared for re-canning. The canning operation provides a coating of metal composed principally of elemental aluminum and silicon with traces of copper and tin, which bonds the aluminum can to the slug. The elements in intimate contact with the slug combine chemically with the uranium to form the tenacious compound layer. The current recovery process consists essentially of a sodium hydroxide-sodium nitrate bath for chemically removing the aluminum can and the bonding medium, followed by hydrofluoric acid and nitric acid baths to remove the remaining compound layer and to pickle the slugs before they are returned to the process canning line. Recent studies have indicated the possibility of using a more economical means of recovery. This includes the mechanical removal of the aluminum can and most of the bonding medium, followed by a chemical removal of the residual compound layer by a solution of sodium hydroxide. A laboratory scale investigation was made to determine whether a solution of sodium hydroxide would remove the compound layer from de-canned, …

The geology of the Hanford-White Bluffs area was studied preliminary to drilling well(s) and developing an underground water supply. A study of the geology of the Hanford-White Bluffs area has shown that it consists of terrace deposits of sand and gravel covering a consolidated sandstone known as the Ringold formation. Beneath the Ringold are successive layers of basalt interbedded with volcanic ash, sand and other materials. In the past the Columbia River has cut channels through the area which extended downward into the Ringold formation. The old channels have been filled and upgraded to the present land surface in repeated flooding of the river over a long period of time. An aquifer used needed to be capable of supplying more than 34 million gallons of water per day.

The installation of crossheader pressure gauges on the reactors has shown that excessive pressure drops occur across some crossheader screen assemblies, and that the pressure drop across the four inch assemblies in the B, D, and F Reactors is significantly greater than the six inch assemblies at the DR and H Reactors. Since the inlet water system pressure is limited to the 4.5 psi discharge pressure of the secondary pumps, the reduction of pressure resistance downstream of that point would result in higher reactor flow rates and increased boiling limits. This test described in this report was initiated to determine if four inch crossheader screens having equal and 50% greater free-area than DR -- H screens would significantly reduce the crossheader screen pressure drops at the B, D, and F Reactors, and to obtain information regarding cone screen plugging rates with larger size screen openings.

This report describes the operation of the fuels preparation department for the month of April 1958. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.

A meeting was held in Wilmington on May 15, 1956, with representatives of Allegheny Ludlum to discuss possible production by Allegheny of uranium tubes in the number needed this next year for development work on tubular elements by Savannah River. Allegheny Ludlum, through king, had expressed a possible interest in the manufacture of uranium tubes. The Allegheny representatives, in the meeting, reiterated their interest in trying to determine whether Allegheny should consider entering the business of fabricating nuclear fuel elements and nuclear fuel element components, pointing out that the did not wish to do this work in existing facilities. Woodhouse covered the work done by Nuclear Metals, Inc., on bare uranium tubes. He stated that this work had reached a stage in which there would be needed, for development purposes, a supply of the order of 500 bare tubes at Savannah River over the next twelve months. These will be in excess of Nuclear Metals ability to supply. King as a director of NMI and Pierce as a former director were familiar with the NMI situation. On question by King, Worthington stated the order-of-magnitude of the tube requirements if the development work is successful and tubes are used on a …

Increased activities in Cryogenic Engineering have brought about the need for a compilation of available data. The purpose of the Cryogenic Data Book is to provide a condensed source of reliable data and reference information for those working in the cryogenic field. Specifically the data were compiled with a view toward the design of liquid hydrogen bubble chambers.

A number of coatings was investigated for protection of graphite against high-temperature oxidation and erosion. Well-sintered, well-bonded silicon carbide coatings were obtained by depositing elemental silicon on graphite, densifying, and sintering in CO at 1300 to 1400 deg C. However, the coatings were not perfect since complete protection was not offered against oxidation. A 75-15- 10 nickelchromium-silicon alloy sintered at 1100, 1200, and 130 deg C wet graphite very well, whereas coatings with high metallic luster were obtained at the higher temperatures. Fecral, alumina, and chromium-silicon-iron-aluminum alloys were deposited electrophoretically on graphite. Although excellent green coatings were obtained, sintered coatings were poor. The fecral coatings did not wet the surface, and the alumina coatings were brittle and non adherent indicating that a higher temperature was necessary. (For preceding period see KLX-10065.) (auth)