This document, dated February 1, 1956, presents the results of a study made to ascertain the most desirable method, both from an economical and operational consideration, of utilizing the acid recovered in the 224-U Building at HAPO.

A large portion of the slug failures which occurred during 1955 were of the ``hot-spot`` type. Observation of these failures has shown them to be the result of intergranular corrosion attack of the aluminum jacket. Intergranular corrosion is presently considered to occur in water temperature above 150 C; a flow disturbance which causes non-uniform coolant temperatures is suspected as the cause of failure.The present of a cocked slug, or a bowed slug column, might provide this flow disturbance. 189-D laboratory tests have shown that flow seating the slug charge allows slugs to cock in the tube. It has also been found that these cocked slugs may be lifted to close proximity of the tube wall by the axial load on the slug column due to process water flow. It is believed that in cases such as this, slug and coolant temperatures may become critical. Present charging procedures allow for flow seating of the slug column. The distance the column is flow seated varied from very little to 3 or 4 inches depending on the particular charge. It is believed that this practice can lead to the situation observed in the laboratory tests. During the past two months, there has been …

This is the monthly report for the Hanford Atomic Laboratories Products Operation, February, 1956. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This report discusses continuing proposals for a continuation of research and development on new fuel elements. Topics discussed are: extrusion cladding of flat plates; internal cladding of tubes; and aluminum-uranium alloys.

This is the monthly report for the Hanford Laboratories Operation, February, 1956. Metallurgy, reactors fuels, chemistry, dosimetry, separation processes, reactor technology financial activities, visits, biology operation, physics and instrumentation research, employee relations are discussed.

The nuclear safety specifications (1) for handling J-slugs have previously been reviewed. These specifications provided information for the storage of loaded 100-hole shipping containers and loaded 66-hole wood cart pallets in certain arrays. Storage of J-slugs in J-Material Crates conforming to Drawing No. H-3-6217 had not been reviewed for the previous specifications. It has become desirable to provide specifications for J-slug storage in these crates as well as make additions to the present specifications on the storage of these enriched slugs in shipping containers and pallets. The results of this study pertaining to arrays of J-slugs in shipping containers and pallets will be incorporated as an addition to the present specifications for handling J-slugs.

The purpose of this proposal is to present a suggested program for the development of an Aqueous Homogeneous Reactor Power Plant for the production of power in the 5000 to 10,000 kilowatt range under the terms of the Atomic Energy Commission's invitation of September 21, 1955. It envisions a research and development program prior to finalizing fabricating commitments of full scale components for the purpose of proving mechanical and hydraulic operating and chemical processing feasibility with the expectation that such preliminary effort will assure the contruction of the reactor at the lowest cost and successful operation at the earliest date. It proposes the construction of a reactor for an eventual net electrical output of ten megawatts but initially in conjunction with a five megawatt turbo-generating unit. This unit would be constructed at the site of the existing Hersey diesel generating plant of the Wolverine Electric Cooperative approximately ten miles north of Big Rapids, Michigan.

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One equipment control building designed to be blast resistant and two each of three standardized types of metal warehouse or utility buildings were exposed to the effects of a nuclear device detonation. One of the utility buildings was frameless, with deeply corrugated wall and roof sections; a second was very largely frameless, utilizing interlocking channel sections; and in the third the aluininum-panel wall and roof covering was supported by girts and purlins, which in turn were supported by steel frames. Because of atmospheric conditions at the time of an earlier detonation in the test series, one of each of the three types of utility buildings was exposed to approximately 0.7 psi overpressure before the planned test. In the planned test one of each of the three types was exposed to approximately 3.0 psi overpressure and one to 1.3 psi, with the intention of bracketing their overpressure survival range and obtaining data for possible economic redesign for improved blast resistance. The equipment control building utilized continuous-welded steel frames and reinforced-gypsum curtain-wall construction. The control building was exposed to approximately 4.1 psi, in the anticipated fringe zone of major structural damage, to determine its protective capabilities. The blast-resistant equipment control building was …

Radiochemically determined mass-yield curves are given for the fission of U/sup 235/ and U/sup 238/ by l4.7-Mev neutrons. Symmetric and to a less extent, very asymmetric modes of fission are more probable at that energy than in thermal fission. Yields of four fission products from the fission of U/sup 235/ have been measured as a function of neutron energy in the range thermal to 14 Mev. The yields of eleven masses have been measured from the fission of Np/sup 237/ by degraded fission spectrum neutrons. The mass-yield curve is similar to that from the thermal fission of Pu/sup 239/ with a ratio of peak to valley yields of approximately 175. Relative yields of one peak fission product and four valley fission products have been determdned under the following conditions: fission of U/sup 235/ and Pu/sup 239/ with thermal neutrons; fission of U/sup 235/ Pu/sup 239/ and U/sup 238/ with fission spectrum neutrons; and fission of U//sup 235/ and Pu/sup 239/ with the intermediate neutron spectrum at the center of the Los Alamos Fast Reactor. Absolute yields of Moss have been determined from the fission of U/sup 235/,Pu/sup 239/ with thermal neutrons. (auth)

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Methods of melting uranium and its alloys are examined including vacuum induction melting and consumable and non-consumable electrode arc melting. The equipment and procedures are outlined with the limitations and uses of each method. In addition, the preparation and properties of Al--U, Cr-U, Mo--U, U-- Nb, U--Si, and U-Zr, and Nb--U--Zr alloys are described. Special techniques of agitation during freezing to produce fine castings are listed along with a discussion of the advantages of centrifugal casting. (J.R.D.)

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Results from studies of irradiation induced transformations in U--Mo and U--Nb alloys are reported. Progress in the development of a satisfactory brazing technique using Al alloy for use with U/sub 3/Si mods in Zircaloy-2 tubes is reviewed. Additional data are given on the corrosion of bare of U--q systems in water. Work directed toward the development of satisfactory UO/sub 2/ for fuel elements is reviewed. (D.E.B.)

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