A preliminary design study of the nuclear gas engine, consisting of a gas-cooled reactor directly coupled to a reciprocating engine, is presented. The principles of operation of the proposed gas engine are outlined and typical variations anre discussed. The nuclear gas engine is compared with other reciprocating engines and air compressors. A comparison between the ideal and actual cycles is made, with particular attention given to pumping, heat, and other losses to be expected. The applications and development of the nuclear gas engine are discussed. (W.D.M.)

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Bench-scale studies were made on use of di(2ethylhexyl)-phosphoric acid in an organic diluent (Dapex process) for solvent extraction recovery of vanadium from acid leach liquors. Vanadium may be stripped from the solvent by either acidic or alkaline reagents, the former having been studied in considerably greater detail. A process for single-cycle recovery and separation of uranium and vanadium from sulfate leach liquors was shown to be attractive both from the standpoint of operation and chemical costs. Process schemes for recovery of vanadium from uranium-barren liquors are also described. On the basis of the encouraging laboratory results, pilot scale tests for specific applications are recommended. (auth)

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An over-all description of the background material on the use of electrical arcs for heating of powders is presented as well as a summary of experimental studies on the arc calcination of thoria. Favorable results have been indicated both with heating thoria powder in an arc heated gas and with thoria formed into a consumable electrode. Use of a consumable electrode produces thoria particles 0.1 to 0.01 mu in diameter. It is recommended that additional electrodes be fabricated and further arc calcination tests be run to produce a quantity of product sufficient for evaluation. (auth)

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Uranium and plutonium were recovered by liquid-liquid extraction from simulated sulfuric acid stainless steel decladding solution with several extractants. Consecutive extraction of U(IV) and Pu(III) or (IV) by 0.1 to 0 3 M primary amine in hydrocarbon-- alcohol diluent appeared promising, and chemical flowsheets were demonstrated in laboratoryscale continuous countercurrent extraction. Extraction of U(VI) with a dialkylphosphoric acid appeared promising when plutonium recovery is not needed. Recovery is also chemically feasible by extraction of U(VI) and Pu(IV) with an N-benzyl secondary alkyl amine or a trialkylphosphine oxide. The amine extracts are stripped with nitric acid, giving a sulfate-nitrate product solution. The organophosphorus extractants permit elimination of the sulfate but require sodium carbonate for stripping. (auth)

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Eurochemic reports were reviewed by BNL personnel concerning aqueous reprocessing, and several comments are offered for process improvements. Also, pertinent BNL documents related to waste and head end processes and corrosion are listed. (J.R.D.)

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An experimentally determined evaluation of standardremote-handling equipment applied to the problems associated with remote maintenance of a typical reactor system component is presented It is comcluded that commercially available equipment can be used and that a good techmician can rapidly learn the use of manipulators required in remote maintenance. The use of closed circuit television in maintenance is possible; however, further development of radiation- resistant equipment is required. (j.R.D.)

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In connection with the Upshot-Knothole test series in network consisting of 95 U.S. and 26 forcign stations was set up. Of the 11 devices detonated, ranging in yield from 0.2 to 60 kt, highier activity was found for lower bursts than from air drops. Information relating to the optimum spacing of stations in a gummed film network and the possibility of missing local areas of intense fallout are discussed. (W.D.M.)

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Some calculations have been made to estimate the characteristics of a neutron-burst type fast reactor similar to Godiva but made up of relatively small component parts--the so-called "layered assembly." One spherical and three cylindrical assemblies have been considered. Critical masses, assuming 5% voids, range from 58 to 65 kg of 93.4% enriched U/sup 235/. For a reactivity addition of 0.33 dollars above prompt criticals bursts between 2 x 10/sup 17/ and 6.7 x 10/ sup 17/ fissions were computed with accompanying temperature rises varying from 514 to 1600 deg C. The burst width at half-maximum was about 12 microseconds. To obtain an idea of the possibilities of stress reduction which might be achieved by layerings an assembly made of small rings was considered. While the critical masses obtained here are believed to be fairly accurates the predictions concerning mechanical energy generated, total fissions, and burst width may be subject to sizeable error due to the many simplitications required to allow hand computations. Neverthelesss considerable improvement in safety and burst-size is indicated by the use of a "layered assembly" instead of an assembly composed of relatively thick parts. (auth)

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The Army Gas Cooled Reactor System Program includes water moderated heterogeneous reactor (Gas Cooled Reactor Experiment I), a graphite moderated homogeneous reactor (Gas Cooled Reactor Experiment II), a mobile gas cooled reactor (ML-1), and the co ordination of thc Gas Turbine Test Facility. The progress of each project, the associated tests and data evaluation, the applicabie design criteria, and the fabrication of reactor components are briefly summarized. (For preceding period see IDO-28538.) (W.D.M.)

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