The following document describes the usage and results of sending pulsed beams of electrically charged particles with electrically wide range of pulse lengths and pulse repetition rates.

Breakaway corrosion of Be in moist CO2 can be avoided if the Be is fabricated using preoxidized powder. The powder is preoxidized by heating in dry O/sub 2/. Preoxidation of Be powder was measured as a function of temperature and time of heating in O/sub 2/. The subsequent reactions of the preoxidized powder in moist CO/sub 2/ at 700 deg C were studied and the effect of increasing amounts of added oxide was measured. A model is proposed to explain the inhibition of corrosion by added oxide. (auth)

This report supersedes ORNL CF-57-2-1, which was an extension and revision of ORNL CF-54-6-72. Details concerning a recommended system of flow-plan symbols and drawing are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. The system is a modification of the Instrument Society of American Recommended Practice (RP 5.1).

In the past it was felt that the easiest way to treat a three group equation for a MTA lattice was to solve it without certain terms. This iterative procedure converged rapidly for a medium with depleted uranium fuel, and in fact, a second iteration was not needed.

At high excitation energies, competition of proton and c-particle emission with neutron emission becomes important. For low excitation, the competition between Y-emission, neutron emission, and fission should be taken into account. To aid in the evaluation of this competition an experiment has been performed to measure the number and energy spectrum of the protons and c-particles emitted in the high energy bombardment of uranium with protons, deuterons, and c-particles.

The Eyewash program, written by James H. Alexander and Nancy D. Given, provides solutions of reactor criticality problems in spherical geometry by means of the group diffusion method. It employs thirty lethargy groups (plus one thermal group) in nine regions. The input consists principally of specifying the geometrical scaling factor, boundaries and compositions of the various regions, and temperature level. The output includes the value of vc that would render the system critical, the relative fission density distribution, fissions, absorptions, and leakages in each lethargy group in each region, and, if desired, an edit of the flux at each space point, each lethargy, and an edit of the macroscopic cross sections for each lethargy, each region. OCUSOL-A is a minor modification and extension of Eyewash. It provides for the computation and editing, on the supervisory control typewriter, of the total absorptions in selected nuclides in the various regions. This information is useful in the computation of breeding ratios and the preparation of detailed neutron balances, and in the estimation of flux-averaged cross sections for use in estimating the rate of change of concentration of the various nuclides with burn-up. The program also provides for saving and transferring the final fission …

From introduction: "This report presents the apparent viscosities of supernate-sludge slurries prepared synthetically to simulate the conditions known to exist in the waste storage tanks, but with fission products and plutonium absent."

From statement of objectives: The purposes of the work described in this report are to provide data useful for designing and operating the dissolver solution clarification equipment to be installed in the Redox production plant.

This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.

Zirflex cladding waste is to be neutralized to pH 10 before transfer to waste storage tanks. This treatment causes the precipitation of zirconium oxide or hydroxide, which may lead to flow difficulties during transfer. The purpose of this investigation was to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selectin of satisfactory transfer equipment and storage conditions.

This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).

The purpose of the Analytical Laboratory Manual is to assemble the basic procedures to be used for the analyses of materials employed within the Fuels Preparation Department. The methods appear in detailed steps suitable for laboratory use. This document replaces the "Essential Material Analytical Manual, " HW-25375 and "Metal Preparation Analytical Manual," HW-30862.

This technical report represents a brief survey of work by this project on the effects of ultraviolet radiation (UV) on certain of the photochemical and metabolic properties of rhubarb chard and sugar beet (Beta vulgaris). These plants were selected for this work because for some years they have been used as sources of chloroplasts for Hill reaction studies in this laboratory. Some of this work has appeared as a brief paper.

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.

The radiation hazards associated with recycled nuclear reactor fuels will greatly complicate the handling and refabrication of these fuels. This problem is most serious with U-233 and plutonium fuels where the presence of U-232 and the heavier isotopes of plutonium contribute energetic alpha, gamma, and neutron radiations at levels many times that from isotopically pure U-233 and Pu-239. This report summarizes present knowledge of the radiation hazards associated with recycled fuel and the additional data needed to make a thorough evaluation of these hazards.

The following document describes the process of rare beryllium extrusion using graphite introductory cones with the purpose of finding a lubricant which would decrease excessive friction between the billet and prose parts.

The determination of various parameters such as thermal utilization, resonance escape probability, control rod calibrations and etc. is often accomplished by the measurement of the pile period due to some given perturbation. With the present thoughts being directed towards plutonium fueled reactors, it was felt worthwhile to discuss a few of the basic differences in pile neutron behavior due to the smaller fraction of delayed neutrons per fission of Pu239 and the larger fraction of delayed neutrons per fast fission of U238 than occurs from fission of U235 alone.

Abstract: "The effect of heat treatment of 2000 to 4650 F on the structure of carbons from several sources have been investigated, using X-ray diffraction. Of particular interest was the effect of temperature on the degree of graphitization. The process of graphitization results in a larger graphite crystallite size in the ao direction, the plane of the layers, than in the co direction. No correlation was found between the structure of the coke heated at 2000 F and the degree of graphitization attained at 4650 F. Materials coked in a closed retort yielded a more perfect graphite structure than the same material coked with access to air. Carbon blacks yield graphite with a greater co lattice constant than cokes with comparable crystallite sizes."

The development of swaging and vibratory compaction process for fabrication of clad UO2 fuel rods is described. The cost is less than 50% of that for an equivalent core fabricated from pellets. The irradiation testing of vibratory filled and swaged UO2 rods is reported for burn-ups from 2,000 to 12,000 Mwd/t UO2; the results indicate that the rods are capable of excellent performance power reactors.

A monthly report summarizing work perform by Babcock & Wilcox personnel for the U.S. Atomic Energy Commission. This month's report includes information on various factors entering into the estimate of reference design core which has been analyzed for sources of error, further design and testing procedures on the nuclear core, and other work focused on construction and design elements.

The objective of this study is to establish a primary loop purification rate for normal operation to (1) maintain the activity created in the primary coolant water by corrosion products and other impurities (excluding fission products) at tolerable level and (2) minimize the crud deposition on the core heat-transfer surfaces.

Abstract: The extent of the reduction of U(VI) by Fe(II) in phosphoric acid solution has been measured as a function of the phosphoric acid concentration (1.9-7.7M) and as a function of the Fe(II)/Fe(III) ratio. Kinetic measurements of the slow redox equilibrium involved conform to a first order rate law. The introduction of fluoride ion into these solutions considerably increases both the reaction rate and the extent of the reduction. The formal electrode potential of the U(IV)/(VI) couple, E'U₄,₆ has been estimated in the range 1.85-4.8M H₃PO₄, from measured E'Fe₂,₃ values in combination with the redox equilibrium data.

From introduction: This is the first in a series of reports describing an investigation of the chemistry of uranium(VI) orthophosphate solutions which is at present underway in this laboratory. Spectrophotometric, potentiometric and solubility studies have been carried out, and it is the first of these which is reported here.

Abstract: "The sensitivity to fast neutrons of a CP Meter ionization chamber of the type used for health physics beta and gamma survey measurements has been investigated."