During the first 15 months of operation of the Redox process, it was clearly demonstrated that in the absence of any pre-solvent extraction treatment of the starting metal solution, ruthenium contributed from 75 to 95% of the remaining fission product activity in both the final uranium and plutonium streams, and that three solvent extraction cycles were able consistently to produce, at best, only marginal quality product. This precarious position was further endangered by a three-fold reduction in the gamma radioactivity specification for recovered uranium shipped from Hanford, and by increased power levels in the reactors, resulting in still higher fission product concentrations in Redox feed solutions. The purposes of this review are to summarize briefly: (1) the chemistry of Ru in the Redox process; (2) the permanganate head-end treatment and its associated problems in plant operation; and (3) alternate possibilities for the elimination or control of Ru, including those which might solve the permanganate process difficulties. It is also the purpose of this document to present a selected bibliography on the subject of ruthenium specifically for those points under discussion herein. 17 refs.

Recent successes with the use of metal ferrocynanides, particularly nickel ferrocyanide, for the removal of cesium from Uranium Recovery Process wastes prompted an investigation into the use of this carrier for the removal of cesium from wastes produced in the coating-removal and first-decontamination-cycle steps of the Bismuth Phosphate Process. Both in-line treatment of the wastes currently produced and treatment of supernatant liquids from wastes already stored in underground tanks were considered.

This document defines the basic criteria to be used in the preparation of detailed design for Project CG-558, Reactor Plant Modification for Increased Production and for Project CG-600, 100-C Area Alterations. It has been determined that the most economical method of increasing plutonium production within the next five years is by the modernization and improvement of the 100-B, 100-C, 100-D, 100-DR, 100-F, and 100-H reactor plants. These reactors are currently incapable of operating at their maximum potential power levels because of a limited availability of process cooling water. As a result of this programs, it is estimated that 1650-2350 megawatts of total additional production will be achieved. The purpose of this document is to set forth the design for certain modifications and additions to Hanford reactors and their supporting facilities as required to obtain higher power levels and improve the safety of reactor operation.

A new slug for U-233 production consisting of a solid thorium core externally jacketed by a thin Oralloy foil is described. Advantages of this system are pointed out. The bulk of this report concerns itself with the long-term changes of reactor parameters as the foil slug is irradiated at constant specific power (kilowatts per foot). Isotope yield curves are also presented.

The carbon cycle of photosynthesis is briefly reviewed in its entirety and the experiments involving it which led to the implication of disulfide rupture in photosynthesis are indicated. A review of the organic, physical and photochemistry of disulfides, with particular reference to the five-membered disulfide rings as they appear in thioctic acid, is given.

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Techniques for producing as-polished surfaces for inclusion studies and etched surfaces for grain studies are outlined. (D.E.B.)

A series of organic reagents for the collection and flotation of several secondary uranium minerals has been developed, this being the mono-alkyl nitrogen substitutions of the dithiocarbamate grouping with a chain length of at least eight carbon atoms. In flotation tests, using the potassium salt of n-decyl dithiocarbamate as collector, high recoveries of autunite have been obtained from mixtures of finely-ground synthetic autunite and silica sand. Certain base-metal salts added as conditioning agents have increased the collecting properties and selectivity of the dithiocarbamates in the flotation of both autunite and carnotite. In single batch and locked tests, using lead as the base metal ion, recoveries of over 95 percent of the uranium have been obtained, with ratios of concentration as high as 13:1. Preliminary tests on natural ores show encouraging results; the problems of liberation and conditioning must be solved for each ore. (auth)

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This report, from the Hanford Atomic Productions Operation, December 10, 1954, presents specifications for a Uranium exposure test in a Hanford Production reactor. Assemblies, canning, and heat transfer are described.