for filtration of plutonium oxalate slurries. A scalpel produces a slit in the filter precoat, leading to increased filtration in this slit, and the oxalate is removed by a doctor knife; this technique results in prolonged blowback cycles and more uniform delivery of filtered oxalate to subsequent processing steps. Several types of filter media were tested, and rigid porous aluminum oxide was found to be the best one. (D.L.C.)

Activities during the period were directed primarily toward determination of the engineering properties of hydrided materials. The tensile strength and elongation, thermal expansion, thermal conductivity, and heat capacity of ZrH were determined as functions of temperature and H content. Preliminary results of Ti-base material studies indicate that these materials can be used for shielding and structural materials with the incorporation of rare earth hydrides. A summary of the work from Oct. l958 to Sept. 1959 is included. (J.R.D.)

Introduction: "This is the ninth letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from August 1 to October 1, 1959."

From introduction: This report summarizes existing subsurface data concerning the thickness, character, and structure of upper Permian evaporites in part of Eddy County, N. Mex. The area of particular interest lies in central eastern Eddy County between Project Gnome site, in the center of sec.

From introduction: This report summarizes the information obtained during preparation of the lithologic log of the core and presents results of chemical analyses of marble samples collected from surface near the drill hole. The report was prepared by the U.S. Geological Survey on behalf of the Albuquerque Operations Office, U.S. Atomic Energy Commission.

The following report discusses direct recording of nuclear pulse height data on magnetic tape that represents an inexpensive method of data storage where some degradation of the original energy resolution can be tolerated.

This report discusses the concept of an improved mass gauging technique with a scintillation counter as the radiation detector in order to meet industrial requirements.

The following document is an updated note on the process of building an improved nuclear density gauge within the time interval of September 2 to October 1, 1959.

The objective of this test is to authorize irradiation of pilot quantities of alloyed dingot uranium and to provide for monitoring of its performance. This test will authorize: (a) Charging of up to 50 tons of alloyed dingot fuel elements in two groups of 25 tons each, including 12 monitor charges which will accompany the first group, into D Reactor as a pilot loading. Although purer and ore dense than standard ingot uranium, the dingot uranium produced in the past by MCW has demonstrated poorer dimensional stability during irradiation. The instability has been manifest as warp, nearly double that of ingot which was irradiated in the same charge and by surface bumping up to 5 mils in height. Both the bumping and the warp are normally associated with large grain size, non-uniform orientation and/or residual stresses. To improve the stability,, primarily by grain size reduction, additions in the range of 150 ppm iron and 100 ppm silicon are being made to the green salt prior to reduction. The hydrogen content of the metal has been reduced by pre-heating the green salt at high temperature prior to triggering the metal reduction. Further refinements to the process include heat treatment in chloride …

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Abstract: "A simple solution to Saha's equation has been obtained. The method of solution involves iteration with respect to the electron pressure or concentration and can be applied to the simultaneous calculations of any number of ions. Sample results are given for lithium and aluminum."

The present quarterly report is the continuation of a series issued by the new Fuels Development Operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations.

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The objectives of this test are to obtain a current knowledge of the H Reactor flow system characteristics under various transient conditions which have a reasonable probability of occurrence. The test data will be used to revaluate: (1) the H Reactor bulk effluent temperature limits, (2) the margin between the Ball 3X riser pressure trip settings, and (3) the quantitative adequacy of emergency flow available from the combined high tanks export system. This test will consist of two parts: (a) Measurement of the flow characteristics during transition from the primary coolant system to the secondary coolant system (190 steam driven pumps.) (b) Measurement of the adequacy of the last-ditch emergency water system (combined high tanks-export system) during a simulated primary and secondary coolant system failure.

Two coextruded, Zr-2 clad, natural uranium, seven rod cluster fuel elements were irradiated to a calculated exposure of 1250 MWD/T in the KER Facility and discharged 1-16-59. The fuel elements were NPR candidate fuel and examination was requested to determine the behavior of coextruded, Zr-2 clad, natural uranium irradiated at core temperatures of approximtely 425{degree}C. The elements were transferred to the Radiometallurgy Laboratory 2-25-59. The elements demonstrated excellent in reactor performance with no significant changes in either the fuel or the hardware. Detailed examination of the central rod and two peripheral rods from one of the clusters showed no microcracks in the uranium. Moderate growth was observed in the fuel at the unrestricted rod ends.

The objective of this Supplement described in this report to Pt-IP-250-A is to d enriched tube-and-tube elements will develop pitting corrosion on the Zircaloy-2 jackets when irradiated in pH 10 water. The measurement of dimensional changes in the fuel elements and the observation of the effect of irradiation on the uranium and bond area are also objectives of the test, but secondary in importance to identifying a pitting corrosion problem in NPR quality water, if one exists.

Introduction: The Office of Isotopes Development of the United States Atomic Energy Commission has requested that Stanford Research Institute prepare a report on the applications of radioisotopes in agriculture.

A .0005 inch thick chemically nickel plated, C-64 aluminum clad, natural uranium, internally and externally cooled, Hanford production fuel element, which had incurred a ``side hot spot`` during irradiation, was shipped to the Radiometallurgy Laboratory in June 1959 for post irradiation examination. The slug vas irradiated to approximately 400 MWD/T in C Reactor as part of PT-IP-207-A. The examination was requested by personnel from Process Engineering, Fuels Preparation Department and Process and Reactor Development, Irradiation Preparation Department to determine the irradiation behavior cf nickel plated fuel elements and to aid in evaluating the nickel plated fuel element program. The presence of the nickel plate probably averted a ``side hot spot`` failure. Al-Si spheroidization and Ni-Al diffusion indicated that the maximum surface temperature vas 325--350{degrees}C for at least one hundred hours, however no sloughing of the nickel vas seen in the ``hot spot.`` Sloughing of the nickel plate, associated with poor nickel bonding, vas observed near the cap end of the slug. The condition my have been aggravated by the formation of hydrogen gas originating from the diffusion of atomic hydrogen through and/or from the nickel plate into the voids between the nickel and aluminum in poorly banded areas. Observations prompted …

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Objective of this production test is to obtain irradiation experience wit the hot-headed closure for co-extruded Zircaloy-2 jacketed rod. Seven Zircaloy-2 jacketed natural uranium seven-rod cluster elements with hot-headed end closures and spark machined end supports will be irradiated in the KER Loops to an exposure of 2000 MWD/T in pH 8--11 coolant.

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Emergency procedures are given for the water plant, effluents, contamination, criticality and storage basin ruptures. For the water supply: a loss of flow to a single tube, loss of flow to several tubes, interruption of river flow, breach of Grand Coulee dam, and evacuation are all considered. For the failure of the effluent system: blockage or rupture of effluent lines, retention basin, or outfall line; and downcomer overflow or failure are discussed. An emergency resulting in the spread of contamination is examined. Hypothetical criticality accidents in dry or wet storage are discussed.

This document details activities of the Fuels Preparation Department during the month of September 1959. (FI)