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.

The primary purpose of this writeup is to present a description of the electrical and mechanical features of the developed system for use in maintenance and operation of a simultaneous scaler control unit.

A method for determining the appropriate isotopic content of uranium-235 in uranium slugs has been investigated. In the conduct of the experiment it was found that there was a background counting rate several times the counting rate of the phenomena under study. Methods are suggested for improving the counting rate and reducing the background. The conclusions at this time are that reactivity determinations will provide the most rapid and precise measure of U-235 content in uranium.

A new type of flexible hose connector consisting of a Teflon tube enclosed in a stainless steel wire braid sheath was proposed for use on 105-C rear face in late 1954. A test was initiated to determine the suitability of Teflon, and specifically Fluoroflex Teflon compound for rear face application. Probable useful life limit is estimated at 10⁶ R, which would be attained in about three years in contact with fresh effluent.

The purpose of this report is to present a HAPO proposal for the design and construction of a high-temperature, high-pressure light water recirculation test facility for the Westinghouse Electric Corporation, Atomic Power Division This report does not attempt to justify the feasibility of site location nor does it attempt to elaborate on such technical considerations as permissible test specimen heat generation and enrichment requirements which have been covered in an earlier document. Instead, detail information is developed on the proposed design with major emphasis on detail descriptions of the proposed loop and auxiliaries, design and construction scheduling and costs, and operating costs.

A plutonium solution of known Pu-241 content was purified by solvent extraction techniques to remove uranium and americium impurities. Portions of this purified solution were then analyzed for U-237 as a function of time. Since the growth of U-237 occurs directly by the alpha decay of Pu-241, these measurements provided sufficient data for calculation of the Pu-241 alpha half-life, which was found to be 2.91 ± 0.50 x 10⁵ years.

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W. J. O`Leary and R. R. Herries visited BMI to review the progress of subcontract research on extended surface fuel elements and on consolidation of Horizons` thorium. 1. Corrosion samples, 1in. diameter {times} 0.180in. thick nickel-plated uranium, which had been press-clad with aluminum at 510{degree}C and 6000 psi, have been on test for 18 days with no evidence of undercutting. Similar samples press-clad with 10,000 psi have been exposed for 7 days with no failures. 2. The hydrogen and chlorine content of as-received Horizons` electrolytic thorium was greatly reduced during vacuum sintering and arc melting. 3. A second lot of Horizons` thorium has been compacted and sintered to provide electrodes for two 9-10 lb. melts. 4. Diffusion couples are being annealed and examined in order to determine the rate of solid solution diffusion of thorium in aluminum.

W.J. O`Leary and R.R. Herries visited BMI in company with C.C. McBride, SRL, to discuss the results of subcontract research on the extended surface fuel element program and to discuss with BMI personnel the programs included in the recent contract extension. A summary of results are given in the following. Double and triple melts from two 9--10 pound ingots of arc-melted Horizon`s thorium showed decreasing porosity. Physical and chemical data, on these as well as on eight previous double melted ingots, are being obtained. The problems involved in obtaining uniform castings of uranium-aluminum alloy for co-extrusion billets were discussed, with emphasis upon those phases to be investigated at BMI. A program was outlined to evaluate the effects of outgassing, by vacuum annealing, on the corrosion resistance of nickel-plated uranium. Data obtained from diffusion studies at BMI show that the mutual diffusion at high temperatures of thorium and aluminum is slow, with the diffusion of the thorium into the aluminum proceeding somewhat faster than that of the aluminum into the thorium. Possible methods of applying an inner cladding of aluminum to a tubular uranium fuel element were discussed. ``Half-dollar`` size uranium corrosion samples, nickel-plated and press-clad with 30-mil aluminum at 10 …

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Study approvals are listed with man-months and date specified. Information and safety agreements were reached. Occupational safety and radiation protection, fuel slug development, instrumentation, ingot rolling, and security violations are discussed topics. Appendices contain information on financial status, pile materials program, instrument development program, and technical division study status. (GHH)

Study approvals are listed for Studies 8506, 8509, 8518, 8519, and 8520 with man-months and program dates specified. Safety and security agreements are listed. Additional topics discussed are: financial status, experimental physics programs, pile engineering division program, and technical division study status.

This document defines the basic criteria to be used in the preparation of detailed design for Project CG-558, Reactor Plant Modification for Increased Production and for Project CG-600, 100-C Area Alterations. It has been determined that the most economical method of increasing plutonium production within the next five years is by the modernization and improvement of the 100-B, 100-C, 100-D, 100-DR, 100-F, and 100-H reactor plants. These reactors are currently incapable of operating at their maximum potential power levels because of a limited availability of process cooling water. As a result of this program, it is estimated that 1650-2350 megawatts of total additional production will be achieved.

This report summarizes work completed during the Redox Plant shutdown in January 1955. An analysis of major difficulties encountered, improvements made during the shutdown, and building design deficiencies brought to light by the shutdown are discussed. (JL)

Production rates of the Hanford reactors can be increased in proportion to the quantity of process cooling water which can be supplied to them. This water must be of such a quality that slug and tube corrosion rates are acceptable, the gross activity of the effluent water must not be excessive, the concentration of specific radioactive isotopes constituting a radiological hazard must be minimized, and the film formation rates should be as low as possible. In the Hanford water treatment process, the filter plants are the controlling factor in determining the quality of the water, and one of the elements limiting the quality of water. A major development effort was therefore undertaken to develop methods of increasing the capacity of the existing filter plants. This report presents the result of this development work from its inception in 1951 to its conclusion in 1954.

Major additions to separations facilities may be required because of increased reactor power levels, reduced exposures; changes in slug specifications, obsolescence of existing solvent extraction plants or development of new separations processes with lower operating costs. The magnitude of first costs for a separations plant is so large as to discourage production planning which would require an additional major separations facility. Experience in separations design has shown that certain process and equipment changes, if they could be developed, would significantly reduce the capital investment in a separations facility. Accordingly design development for a new separations facility is under way. The purposes of this document are to present the results of the first separation design study directed toward a new solvent extraction plant and to summarize process, plant, and equipment changes which should be developed to achieve significant capital and operating cost reduction.

This document has been written because of a request for information from the Advisory Committee on Reactor Safeguards. Hanford operating experience has been summarized in terms of operating hours, startups and scram analysis.

Nine technical studies were approved for funding. Discussions at the meeting centered around safety and work schedules. Appendices contain information on Financial status, the Separations program, the Analytical Chemistry program, and the Technical Division studies that were approved at the meeting.

This document details activities of the Hanford Atomic Products Operation (HAPO) during 1954.

This report provides the weather that pilots observe while in flight.

From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.

Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."

This report discusses three experimental methods used to study the kinetics of the reaction between zirconium and UO2.

From abstract: "Plamons (plasma-magnetic entities) are toroidal "packages" of plasma wrapped up in their own magnetic field. Experimental evidence for the existence of plasmons is adduced and theoretical considerations concerning their various types and their stability are discussed."