Pile temperature control is normally maintained by using four horizontal rods, two ``long`` rods extending to the far side of the pile and two ``short`` rods whose tips are on the near side. (1) This procedure prevents cycling of ``hot spots`` about the pile, but does not achieve symmetrical horizontal temperature distribution. Prior to pile operation the cadmium-containing cans were removed from the near ends of the two ``long`` control rods, numbers 5 and 11, at C pile, so that when these rods were in the ``full in`` position their poisoning effect outside the flattened region at the near side of the pile would be small. By using these ``half rods`` in conjunction with ``short`` rods it was expected that a nearly symmetrical horizontal temperature distribution could be maintained. A comparison of near-to- far temperature distribution at C-pile with other piles indicates that gains in production of 4% during early operation of a pile and 3% during later equilibrium operation can be realized by using the half-rods. On the basis of these observations ``half-rods`` are to be incorporated in the K-piles currently under construction. It is recommended that the ``long`` control rods in existing piles be replaced by rods altered …

This document presents a summary of work and progress at the Hanford Engineer Works for May 1953. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

This is a listing of the classified periodic and series reports originated at the Hanford Atomic Products Operation for the period 1943 to June, 1953, and of similar reports received from the Hanford Operations Office. This listing also traces the continuity of reports that have undergone title changes during this period. This has been done by cross referencing to titles previously or subsequently used. The primary grouping of these reports is according to the intervals at which they were issued, e.g., weekly, monthly, annually, etc. Within each group, the reports are arranged alphabetically by title; for each individual title a note at the right hand margin gives the inclusive dates for the period during which reports of that title were issued. Those not shown with closing date are being issued currently. Specific document numbers for each title are found in the catalogs of the 700 Area and 300 Area Classified Files. The list is intended primarily to assist Classified Files in locating periodic reports requested by Plant personnel. However, it is also hoped that it may emphasize to authors the need for retaining an established title for a periodic report. Unnecessary changes of title every few months for the same …

Analysis indicates that, in order to achieve supersonic flight with nuclear powered aircraft, a reactor -power plant combination capable of operating at temperatures considerably in excess of current practice must be developed. It is pointed out that there exist two general avenues of approach toward the goal of attaining high temperature reactors and power plants. The first approach involves the continuation and augmentation of research along the lines pursued by the conventional turbo-jet engine manufacturer, namely a search for material coatings or materials that will retain structural strength in high temperature oxidizing atmospheres. The second approach seeks to take advantage of the peculiar characteristics of the compressor-jet engine that permit the operation of the high temperature components in a non-oxidizing atmosphere. The results of a preliminary design study of a supersonic aircraft powered by a high temperature sodium, liquid vapor compressor -jet engine are summarized. The analysis considered, in as much detail as was warranted by the limited experimental information available, the characteristics of the reactor, power plant and airframe involved in determining performance. This study has been conducted for the purpose of guiding future, long -t e r rn , research work along the lines of high temperature reactors …

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The elastic differential scattering cross section of 190 MeV deuterons by protons has been measured from 15 degrees to 170 degrees in the center of mass system. The cross sections were obtained by subtracting the carbon counts from those received with a polyethylene target. Part I presents a description of the experiments. Results are shown in Table IV and Fig. 3. Part II compares these results with those expected from theory by making use of a method developed by Chew. A summary of this comparison is given in Table VII.

Brief notes from a meeting between NAA and S. B. Roboff, Sylvania Electric Products, regarding the important developments in powder metallurgy fuels and reactor materials.

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Searches for methods of sterilization of foods so as to overcome changes in flavor, texture and color caused by customary sterilization procedures.

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Power Breeder Reactor. Conceptual design studies for the Power Breeder Reactor indicate the feasibility of a contained primary coolant system in a package arrangement. One- and two-group calculations are presented in detail for preliminary PBR estimations. A technique for impregnating UO/sub 2/ with NaK has been developed. The resulting putty-type fuel was successfully extruded tbrough a 3/8-in. hole. Data are presented on the fuel element design factors imposed by heat transfer and cooling limitations for fuel plates, pins, and spheres. Fission heat liberated in the PBR blanket was estimated to be 7.7% of the total core power. Design criteria resulting from this estimate are analyzed. Heat exchanger size for the transfer of 500 Mw of heat from Na to NaK has been calculated for the intermediate exchanger and for the NaK-toH/sub 2/O steam generator. A theoretical treatment is presented for the thermal stress analysis of stainless steel-clad U fuel plates. Boiling Reactor Heat Transfer Experiments. Further results have been obtained from natural-circulation boiling-density tests and investigations of natural-circulation flow rates. A special thermocouple design, meeting the rapid-response requirements of high-power plate transients, is described. Feasibility studies on heavy water boiling reactors are presented for spherical boiler, pressurized tube, and horizontal …

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This report is about The Chemistry of Uranium(VI) Orthophosphate Solutions. a series of reports describing an investigation of the Uranium(VI) Orthophosphate system.

The applicability and refinement of various procedures for the treatment and digestion of C-slags and other uraniferous residues for recovery of U values were studied. The recovery of U from BFC-6 was investigated, placing emphasis on procedures which will not chemically alter the Cu and Sn media. Methods of U recovery from various residues resulting from Na/sub 2/CO/sub 3/ digestion of miscellaneous U-bearing materials, to reduce the U/sub 3/C/sub 8/ content below 0.05%, are discussed. (W.L.H.)

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