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The isotope Na{sup 24} is one of the major short half-life constituents of reactor effluent water. It has a half-life of 15 hours and decays of emission of a 1.39 MeV maximum beta particle. Other radioisotopes present in reactor effluent water from which Na{sup 24} must be separated are Si{sup 31}, P{sup 32}, Mn{sup 56}, Cu{sup 64}, As{sup 76}, Sr{sup 91--92}, Ba{sup 139--140} and rare earths. This report describes a rapid and very simple method for the quantitative determination of Na{sup 24} in a radiochemically pure form.

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A considerable number of major improvements have been made in experimental facilities this quarter. These include four targets, three air locks, a deep well, and several thin windows for beam extraction in the target area. Simultaneous operation of up to five experiments has been achieved with a relay-controlled automatic operations selector. A beam-amplitude regulating device has been used to set the beam level on any pulse to within a few percent. The range of this equipment is 1000:1. Experimentation on the accelerator this quarter included measurements of start frequency and frequency-tracking jitter, beam-versus-radial-aperture measurements, empirical study of gas scattering effects, and preliminary testing of an automatic beam-controlled frequency-tracking system. High-energy physics experiments have been performed by ten groups within this laboratory. These groups are using counter techniques for the elastic proton-proton scattering, K-particle half-life determination, and {pi}{sup -}-meson cross-section measurements. A high-pressure hydrogen diffusion chamber is being used to study multiple production of {pi}{sup -} mesons. A strong-focusing pair spectrometer has been used to produce beams of K particles. Emulsion exposures have been made to determine the masses and mean lifetimes of K mesons. The interactions and modes of decay of K{sup {+-}} mesons at rest, as well as in …

A discussion is presented of the elements, or at least most of the elements, that are usually thought of as required and characteristic of living materials. A continuous evolutionary process is conceived, beginning with a bare earth and leading to the random formation of more or less complex molecules from simple ones, and gradually, by the processes of random variation, autocatalysis, and selection, to more complex systems and the ordered array of desoxynucleic acid molecules which are the units that carry the continuity and order of present-day living systems.

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The intent of this study is to establish more completely the justifications for constructing a decontamination plant as outlined in Budget Item B 5720, ``Containmented Equipment Renovation Shop,`` FY 1957, Plant and Equipment Projects. In particular, the economic incentives have been explored. The question or idea has been investigated of assigning a dollar value to engineering information which might be obtained from examining contaminated equipment which has failed from unknown causes. Heretofore it has not been possible to examine such equipment because suitable decontamination facilities have not been available. An effort has been made to uncover all possible uses for the proposed facility in order that the estimated capital and operating costs might be evaluated in terms of all the functions which the proposed plant might perform.

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The operation of a Priest Rapids dam is stated to necessitate river flow manipulation varying from 25,000 cfs to 120,000 cfs in the winter months of a critical water year. The low flow may persist for periods of six hours daily, and the expected daily average low flow is 61,000 cfs. The possible effects of this on reactor operation and waste disposal to the Columbia River which are of the interest to the Radiological Sciences Department were reviewed by J.F. Honstead, R.E. Rostenbach, and R.F. Foster. These include radiation hazards in reactor area water treatment plants, reactor area drinking water contamination; increased river temperature; chromium pollution problems; effects on downstream river usage, and effects on aquatic life.

Large groups of Sprague-Dawley rats were given either small single intravenous injections of 0.75, 0.5, or 0.25 microcurie of Po/sup 210/ per kilogram body weight; or repeated doses designed to maintain a relatively constant polonium burden of 0.01 microcurie per kilogram body weight. Since the most sensitive criteria of polonium damage had been shown to be shortening of life span, or possibly increased tumor incidence, these two possible effects were given the most attention in observations continuing throughout the adult life of the animals. Definite shortening of life span occurred in male rats that had received the single doses of 0.75 or 0.5 microcurie per kiiogram body weight. Life span shortening at the 0.25 microcurie level was not as definite, though probable. None of the groups of females receiving single doses showed significant life span shortening, possibly in part because of the greater variance of the female populations. A maintained polonium burden of 0.01 microcurie per kilogram body weight was completely without measurable effect. No effect on tumor incidence was observed in any of the single or multiple dose groups. However, the tumor incidence in all groups of old injected and control rats was very high. (auth)

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An estimate was made of the upper bound for the half-time of dissociation at 100 atm for ammonia, methane, and propane at 2500 deg K and hydrogen at 5000 deg K. In each case a unimolecular reactron in the homogeneous gas phase was chosen as most suitable for this purpose. Slater's theory has been used to estimate the necessary frequency factors. The upper bounds to the half- time for dissociation range from 3 x 10/sup -7/ to 6 x 10/sup -6/ sec. Extrapolation of decomposition rate data obtained at --1000 deg C and 1 atm pressure gives smaller values for the half-time of dissociation. (auth)

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This document discusses a production test which was written when the piles were operating under a graphite temperature limit of 410 C. Operation was controlled by as-read temperatures of the originally installed G thermocouples, by thermocouples installed on vertical safety rod thimbles, and by thermocouples in graphite cylinders installed in the C test holes. Since the thimble thermocouples were to be removed under the Ball 3X program, it was planned to install thermocouples in some of the process tube channels to help monitor the graphite temperatures. In order to ensure maximum production levels based on graphite temperatures, the proper temperature relationships between the channel thermocouples and the G and/or C test hole thermocouples were needed. The expected maximum allowable channel thermocouple temperature reading would be higher than the burnout temperature limit of the graphite in the-pile.

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This document presents a summary of work and progress at the Hanford Engineer Works for July 1955. 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 summarizes 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.

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8 5 6 2 0 5 8 5 5 ? 5 : tion of the HRT is summarized. The design of some reactor components is described, including fuel system line coolers, the thermal shield, instrument cubicles, the reactor cell air monitor, and sampling facilities. The important design specifications for the HRT fissionproduct adsorption system are outlined. The effects of fluid circulation on HRT stability, the results of the rupture of the fuel inlet nozzle on the pressure vessel, core tank temperature, and heat generation and temperature distribution in the control room area shield were examined. Operation of the HRT mockup loop is summarized. High generalized corrosion rates and U precipitation were observed when 50 ppm oxygen was used. Results from tests of HRT pumps, heat exchanger, sampler mockup, and reflex condenser and recombiner are presented. Design of the instrumentation in the control room area and fabrication of differential pressure and liquid level transmitters are reported. Thorium Breeder Reactor. Stability criteria, the effect of slurry settling on reactivity, and neutron losses due to coating the core tank with platinum bave been analyzed for the TBR. An economic study of partial fuel costs for one-region Pu-U reactors was completed. The design concept …