This report describes the operation of the fuels preparation department for the month of August, 1957. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.

The object of the work was to determine the molecular structure of AlH/ sub 3/, using the techniques of nuclear spin resonance.'' Attempts to prepare ether-free AlH/sub 3/ that were unsuccessful are described. Also it was not possible to observe the deuterium signal in AlH/sub 3/. It was possible, by the use of the proton signal of the ether in AlH/sub 3/, to obtain the nuclear spin resonance absorption curve for AlH/sub 3/ by subtracting out the contributions of the ether protons to the resonance signai. A model is proposed to explain the features of the nuclear spin resonance absorption curve. The existence of LiAl/ sub 2/H/sub 7/, which has been postulated elsewhere, is assumed in order to explain the datu obtained from high-resolution nuclear spin resonance experimeats. (auth)

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The preliminary work done by Westinghouse on properties of materials suitable for the in-pile testing facility was reviewed. Information was collected on a selected list of promising materials in the following classificrtions: alloy steels, chromium steels, precipitation-hardening stainless steels, and superalloys. On the basis of the information obtained from Westinghouse, from the literature survey, from Battelle files, and from visits to producers, it is recommended that Phase II of the program be confined to Inconel X hot rolled and aged, AM-350 subzero cooled and tempered, and Discaloy solution treated and aged. (auth)

The Pool Type Critical Facility (PTCF) is a low powered, highly eariched (90 to 95% U/sup 235/) ordinary light water cooled and moderated, beryllium oxide reflected assembly. It is generally similar to the present BSR at ORNL, the principal modification being that the grid plate is arranged to accommodate both ORR and BSR fuel elements. The PTCF is located in the northwest corner of the existing BSR pool. The 9 x 7 lattice provides 63 fuel, control rod, or reflector positions. (W.D.M.)

A study was conducted to obtain information to be used as a basis for recommending cleaning and maintenance procedures for the SRE main primary sodium pump. Results and recommendations are summarized. (J.R.D.)

The status of the overall schedule for design, fabrication, and installation of the component items of the PAR loop experiment in the ORR has been brought up to date and reviewed. This is the first review since the original issue of the schedule