This progress report from the Argonne National Laboratory covers the work in Biological and Medical Research, Radiological Physics, and Health services for the quarterly period ending March 31, 1952. Numerous experiments were conducted in an attempt to answer some of the questions arising from exposure to ionizing radiation, especially X radiation. Some of the research involved the radiosensitivity of cells and some involved animals. The effects of radium in humans was also evaluated. Other studies were performed in biology, such as the effect of photoperiodism on plant growth and the biological of beryllium.

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.

The fifteenth quarterly report being submitted for Contract No. AT04-1-GEN-12 is issued in accordance with Service Request Number 1 except for the report of the Alamogordo Section, Code 91810, which is submitted in accordance with the provisions of Service Request Number 2. Work is in progress on continuing existing projects. In addition, new projects have been initiated including the Kinetics and Mechanism of Protein Denaturation (10018); The Effect of Irradiation on the Constituents of Embryonic Serum (30033); and The Use of Controlled Atmospheres for Spectrographic Excitation Sources (40053). Many of the Project units are either wholly or partially completed and the following initial reports are available: Identification of Ferritin in Blood of Dogs Subjected to Radiation from an Atomic Detonation (UCLA-180); The Nutritional Value of Intravenous Tapioca Dextrin in Normal and Irradiated Rabbits (UCLA-181); The-Decarboxylation and Reconstitution of Linoleic Acid (UCLA-183); Preparation and Properties of Thymus Nucleic Acid (UCLA-184); The Radiation Chemistry of Cysteine Solutions Part II. (a) The Action of Sulfite on the Irradiated Solutions; (b) The Effect on Cystine (UCLA-185); A Revolving Specimen Stage for the Electron Microscope (UCLA-178); An Automatic Geiger-Mueller Tube Tester (UCLA-186); The Value of Gamma Radiation Dosimetry in Atomic Warfare Including a Discussion of …

Physical data are presented for transverse CSF samples with capsule exposures of 568, 1049, and 1617 MD/CT. The higher exposures indicate a sharper damage gradient toward the front of the pile. Additional casings of various types of graphite were loaded into test holes during this month. Average values of the thermal conductivity and electrical resistivity for several types of virgin graphites are presented. Data of this nature will be a regular portion of this report henceforth. Process tube channel 2677-H was mined and traversed for bore diameter. Although several of the tube block junctions were obscured, the channel was quite uniform. Examination of all previously mined graphite powder samples for aluminum oxide corrosion product has been completed and the results are reported.

A healthy 39-year-old male weighing 65 kg was exposed for a period of 8 months to varying levels of HTO. The average tritium activity in body fluids over the entire period was 23 {mu}c/liter. A few weeks after exposure, when the HTO activity in body fluids had declined to about 0.2 {mu}c/liter, a biopsy was pe formed on skin and fat taken from the region of the lower abdomen, and the material was analyzed for tritium activity. The skin showed an average activity equivalent to 0.4 {mu}c/kg of dry tissue and the fat about 0.3 {mu}c/kg of dry tissue. The radiation dose per unit time from these activities was only 1 to 2 percent of the radiation dose per unit time during the 8-month exposure period. It was concluded that the radiation hazard due to retention of tritium in the organic components of these tissues of man after chronic exposure was negligible compared to the radiation hazard from HTO activity in the body fluids which was necessary to induce the activity into the organic components. Comparable experiments on mice previously reported indicate that this conclusion may hold for all tissues in the body. The water content of the skin and …

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This document details activities of the Chemical Development group of the Separations Technology Division during the month of December 1952.

The Redox Plant operated at a 76.7% time efficiency (IAF basis) and averaged 3.16 tons of uranium per operating day during the month. During the period from July 4 through July 13, 38,000 gallons of 72% ANN from Tygon-lined storage tank SS-112 were used in aqueous salt solution make-ups with some emulsion difficulty and fission-product carry-over resulting. New ANN, from stainless-steel tanks, was used for the balance of the month. An extensive (thermally) hot 60% HNO{sub 3} cleanout was given to the IA, IB, 2D, 3D, 2A, and 3A columns and associated salt solution head tanks to prepare the solvent-extraction battery for operation using 90-day `cooled` uranium. Continuous cross-over oxidation to improve 2A Column waste losses, and employment of KOH (vice NaOH) in 2DS, ICU, and 2EU butt additions to minimize Na in 3EU, were begun concurrently on July 20. Aged (90-day) uranium in head-end treated feed batches, was started to the IA Column on July 21, with early data indicating adequate two-cycle decontamination for both uranium and plutonium.