Siimplified shielding calculations indicating the proposed design for the water boiler assembly will reduce the radiation at normal operaton to values well below those which are considered tolerable.

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The success attending the use of azaserine as a specific inhibitor of one atage in the metabolic pathway leading to the synthesis of inosinic acid in pigeon liver prompted us to use this antibiotic in a similar attack on purine synthesis in Scenedesmus. However, investigation of the products produced during photosynthesis by suspensions of these algae in the presence of azaserine showed that a more widespread interference with metabolism had occurred. The purpose of this communication is to describe the nature of these effects and to attempt to assess their importance in a general picture of the metabolic effects of azaserine.

Relationships between surface appearance and actual depth of damage of sub-fabric burns have been established for only a few burns. Since surface appearance has been the most widely used criterion for evaluating the ability of fabrics to protect against radiant energy, it is of some importance to know whether or not bare skin and sub-fabric burns of similar appearance are of comparable severity. In this experiment it was found that both types of burn when produced by one second exposures and when graded 3/sup +/ moderate because of their surface appearance are, indeed, equally severe. Observations on healing of the two types of burn suggest no differences in the manner or rate of tissue restoration. (auth)

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The techniques for assembling, processing and handling large nuclear-emulsion stacks are discussed. Results of experiments varying the development procedure are presented.

The objective of this report is to review the performance of the Redox air-filtration facilities and to present recommendations, resulting from this survey, which could improve the ventilation systems of future Separations Plants. 4 refs., 3 figs., 2 tabs.

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(1) A comprehensive investigation of methods for the preparation of hydrides of wolfram has been made. A wolfram (IV) hydride-aluminum hydride mixture has been prepared and its N{sub H} and thermal stability determined for its evaluation as a nuclear radiation shield material. Aluminum borohydride has been shown to reduce wolfram (VI) chloride to a subchloride. The alkali borohydrides also reduce hexavalent wolfram, but in no case has a wolfram borohydride been isolated. (2) An investigation of the chemical and physical properties of thorium borohydride, which pertain to its use as alow-temperature nuclear radiatin shield, is presented. Values are taken from the literature when available and are supplemented where necessary by our experimental investigation.

Studies of carbon dioxide fixation in green plants using the C{sup 14} isotope have shown that in very short times phosphoglyceric acid contains most of the radioactivity. The tracer is present almost entirely in the carboxyl group. The importance of organic phosphates in the subsequent metabolism of phosphoglyceric acid can be seen from the accompanying photographs.

The radiological aspects of a proposal to recover some of the heat now wasted in cooling water from the Hanford reactors by using the hot water as boiler feed for the steam plants in the 100 Areas are evaluated. The radioactive material in the hot effluent water will contaminate the boiler feed water system, cause additional radiation exposure of personnel, and increase the cost of maintenance and radiation protection, but very little radioactive material will be carried over into the steam system. At present steam loads, this proposal is economically attractive; other proposals being considered may nullify any savings from this one. 21 refs., 1 fig., 10 tabs.

Since 1945 the routine production of plutonium (``A`` buttons) at Atomic Energy plants has been accomplished by heating mixtures of plutonium tetrafluoride, calcium and iodine in crucible-bomb assemblies. Yields above 97% and metal of adequate purity are consistently obtained by this process. Plutonium (``X`` button) production has also been carried out routinely by including plutonium turnings with the powder mixture given above. A majority (several thousand) of buttons produced in the 234-5 Building have been ``X`` buttons made by recycling up to 1.1 units of turnings/unit of plutonium in the plutonium tetrafluoride. Operating hazards exist in either process, however, and these are reviewed below.

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The single-operation alpha counter, designed primarily for counting low-level alpha samples prepared by plating activity onto metal cylinders, was evaluated as a possible replacement for the parallel-plate counters now used to count activity plated on disks. Each cylinder is closed at one end, so that all activity plated on it is on an outside surface which faces the sensitive volume of the chamber, and the total activity of the plate can be determined by a single count. Each side of the disk must be counted separately in the parallel-plate counter, and the edge may be counted twice. Results from about 300 cylinders and 300 disks ranging in activity from 0 to 80 counts per minute were compared. The single-operation counter was found to be capable of giving results at least as good as those obtained with the parallel-plate counter and in half the counting time. The following changes were suggested in the final model of the instrument: (1) redesign of the chamber for more effective decontamination, (2) design of a tool to be used for inserting and removing cylinders, (3) addition of a pressure gauge to the chamber, and (4) an improvement in the method of sealing the chamber to …

A high-density concrete shield is proposed for the biological shield. Adequate shielding of personnel and equipment can be obtained for about two-fifths the cost of a laminated shield of steel and masonite. The proposed shield is expected to behave satisfactorily during the life of the Reactor Unit and, in addition, the shield will possess considerable resistance to earthquake and blast loads. Details of design specification are given.

Discussed is reactivity measurements on fast metal systems and moderated systems (graphite, BeO) used in rocket propulsion, pulsed neutron techniques used in graphite moderated systems, and BeO-U{sup 235} systems.

The vapor pressure of bromine trifluoride has been measured over the range 39 to 155 C. and the following equation was derived by methods of least squares to represent the experimental data. log{sub 10}P{sub mm} = 7.74853 - l685.8/(t + 220.57). The heat of vaporization was estimated from the following equation which is based upon the Clausius-Clapeyron relation. {Delta}H{sub cal/mole} = 7714 [(t + 273.16)/(t + 220.57)]{sup 2}. In continuation of the program to measure the physical properties of interhalogens, the vapor pressure of bromine trifluoride has been determined. Ruff and Braida (4) measured some of the physical and chemical properties including the vapor pressure over a limited range, 4 to 136 mm. The present investigation extends the vapor pressure data to 2 l/2 atmospheres on material of high purity.

This monthly report details the 100 Area technical activities of the Physics Group for the month of May 1950.

This document discusses a meeting held to inform members of the Biology Division of the status of P-10 problems, to exchange ideas on methods of attacking these problems, and to consider new problems.

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.

The objectives of the test described in this report are to evaluate the integrity of I & E MINT fuel elements canned by the ``C`` process to determine the conversion ratio of I & E geometry E-N ``striped loadings,`` and to provide a demonstration loading for a full reactor loading incorporating a ``striped`` center loading and a fringe ``blanket`` loading. This test will involve two portions a 26 tube block loading of I & E enriched uranium and MINT fuel elements arranged in a striped array, and a 10 tube fringe blanket loading of MINT fuel elements supported by the required enriched uranium fuel columns, and accompanied by controls. Either portion may be charged independently.

This report discusses research and engineering work on the purex and redox processes at the Hanford Engineering Works in May, 1959. (JL)

This report addresses the continuous plutonium isolation contactor.

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