It is considered appropriate occasionally to make independent checks on the effectiveness of the plant laundry in removing radioactive contamination from plant-issue protective clothing. Previous surveys have offered constructive criticism resulting in improved handling of high level and soft beta contaminated clothing and incorporation in new designs of ventilating and air sampling recommendations. Recurrently the adequacy of laundry reject limits is questioned, and only recently an accurate, special study resulted in relaxed limits for Metal Preparation area clothing. A current question concerns the advisability of determining the reject level on the beta-gamma monitor more frequently than once a day. 2 tabs.

This document presents a summary of work and progress at the Hanford Engineer Works for September 1952. 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 summaries 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.

This report is a memorandum requesting that two swaged thorium rods being held a MIT be sent to the Savannah River Plant for examination. The memorandum is dated October 15, 1952.

An analysis is made of the heat produced by the absorption of gamma rays in a sample placed into a reactor. It is clearly shown that enormous local (space) variations in gamma flux exist in current reactors. An application to the Hanford reactors is treated in some detail. Although the estimates obtained may be good to but a factor of two, it is clearly shown that in most cases the major portion of the heating is due to (n, {gamma}) reactions within the sample itself, and in some cases to the gamma rays generated in liners and cans, and not from the gamma rays generated in fission, nor from the moderator. Some implications of these results are discussed, among the most important being their application to radiation chemistry in reactors. Several mathematical results for absorption and generation of gamma rays in various bodies which should be useful in estimating dosage rates for samples irradiated in reactors are given (Appendix II). A method for making the calculations for an arbitrary absorption law are given (Appendix III). This method may be used with the true absorption law for gamma rays or even for the calculation of the absorption of the energy of …

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Thermal conductivity data are reported for some mixtures of UO/sub 2/ with MgO, BeO, and Zr; U with Zr and Mg; several amaples of B/sub 4/C; and two ceramic insulators. (auth)

The densiies of uranyl sulfate water solutions were measure or 12 concentrations between the temperatures of 20° and 90°C. The density range at 20°C is 1.0539 grams per cubic centimeter at 0.17 molal to 2.0059 grams per cubic centimeter at 3.9 molal.

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The preliminary results of a program designed to evaluate methods for preparing uranium hydride from the various oxides of uranium are presented. The apparatus has been designed and constructed for the purpose of carrying out batch reductions under a variety of conditions employing calcium hydride, calcium metal and magnesium metal as the reducing agents. Since the separation of the alkaline earth oxides, present as by-products in the furnace products, promises to be the most difficult problem encountered in this investigation, a major portion of thetime during this past quarterly period has been directed toward the development of a suitable leach method. No investigation of the reduction methods has been possible to date because of the inability to obtain SF materials. A brief outline of the future work is included. (auth)

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This document provides the process specifications for the Triple Dip Process for Alpha Fabricated Uranium for production canning of uranium cores.

Redox effluent for production was first processed in the 231 Building on February 4, 1952. Samples of process streams were taken after each purification step to evaluate the adequacy of purification processes in,the 231 and 234-5 Buildings and to provide close control of this material. Data regarding pile residence histories, radiation surveys of ``Sample Cans``, reduction yields, C/Q values, and product purity after purification steps were accumulated and are presented in this report to establish preliminary data which may be used to evaluate future process changes.

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