Investigation report of new artificial heavy nuclides conducted at the laboratory.

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This document presents the monthly reports of the 200 area technical group for July--December, 1947. (KS)

Progress is reported on the topics of extrusion and canning. The information on canning is broken down into: Production test 313-74-M, studies of aluminium cans, selection of surface rejection standards, thorium, and the effect of high and low tin in bronze on tin carry-over to canning bath.

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This is a brief review of the status of the Redox Solvent Extraction Process. Two alternative flowsbeets are included. Planned and current operations are indicated.

Three individuals were inadvertently exposed to polonium. Activity determinations on the routine weekly urine samples submitted by the individuals revealed counts of 174, 734, and 2190 c/min/50 ml respectively. An investigation was immediately launched to determine the source of the exposure, since there was no report of a spill or accident involving active material. By the process of elimination, the time of exposure was narrowed down to a time when two of the individuals were engaged in the denitration of a polonium solution in a small kettie inside a hood when a leak developed in the kettle. The active solution was transferred from the kettle to a carboy. All three individuals were present during the transfer period. Two wore respirators, rubber gloves, and smocks over their coveralls while the third stood well behind and watched the procedure. However, it was concluded that an inhalation exposure resulted. A medical study of each case was instituted and data are summarized. No immediate toxic effects were observed. (C.H.)

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The authors have produced and identified two new series of alpha-particle emitting radioactive elements; one is a 'collateral' branch of the actinium (4n + 3) radioactive family and the other is collateral to the thorium (4n) family. The series are of considerable interest in that they are the first whose early members lie on the neutron deficient side of beta stability. They have been produced in high yield of irradiation of thorium with deuterons of energy about {sup 80}Mev in the Berkeley 184-inch cyclotron. So far as the present observations are concerned both of these series begin with isotopes of protactinium (atomic number 91), although progenitors with higher atomic numbers are to be expected and will possibly be produced and identified. These protactinium isotopes are Pa{sup 227} and Pa{sup 228} formed by d,7n and d,6n reactions respectively.

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Various biochemical effects of radiation have been studied in 10 patients given total body x-ray in total doses of 75 to 310 r (skin), in 5 patients given 20 to 36 mc. P{sup 32}, and in 5 project personnel accidentally exposed to excessive doses of external radiations. Similar studies have also been made of several hundred Plutonium Project personnel exposed in most instances to relatively small amounts of uranium, lead and other metals, and to chemicals and radioactive sources. These studies included the investigation of liver function, of white blood cell chemistry, and of various urinary constituents such as coproporphyrin, urorosein and other pigments, urobilinogen, ``corticosteroid-like`` substances, catalase, and uranium. Definitely excessive exposures resulted in various abnormalities in the above tests. With the exception of urinary uranium analysis none of them are specific in indicating overexposure to either radiation, metals, or chemicals. When interpreted in the light of the exposure and medical history, however, it is felt that they may aid in the clinical interpretation of relatively marked overexposure at least. In addition, they may afford further insight into the nature of radiation effects. The literature on the biochemical effects of radiation is reviewed briefly, and certain suggestions are offered …

Research progress was reported in the following areas: (1) plutonium ingestion studies - rates of excretion, fecal and urinary, were determined for subjects who had drunk a solution containing plutonium; and (2) plutonium therapy studies - rats injected with plutonium were administered zirconium citrate and the rate of excretion of the plutonium measured. (ACR)

This semiannual report includes references in future items in the Brookhaven National Labratory program as well as an account of progress in the post six months.

This is a progress report from Brookhaven National Laboratory for the period July 1 through December 31, 1949.

The objective of this report is to investigate the feasibility of obtaining uranium from the carnotite sludge in such a form as o permit its use in the brown oxide purification process.

The constant temperature bath is in operation. A ballistic type instability was detected in the calorimeter circuits and corrected by grounding the bath. Calorimeters 37, 39, 40, and 43 have been installed are now being run. Calorimeter 40 was found to be unstable, and is to be disassembled and examined for the trouble. Calorimeter 46 was finished and placed in operation. Construction details are discussed. Six Logac samples were run in Calorimeter 38. Tests of this calorimeter are in Table 1. Comparison of Calorimeter 38 in a water bath and in an ice bath is shown in Table 2. Good results were obtained for such a drastic change in environment. Calorimeter 38 was turned over to Calorimetric Assay marking the end of the tests of this particular microcalorimeter. Calorimeter 44 was completed and installed in the ice bath. Table 4 shows the results of tests. The zero bridge potential is small and is very stable compared to Calorimeter 38. The comparison of the values with those from Calorimetric Assay is summarized in Table 3. The characteristics of Calorimeter 44 are shown in Table 5. Construction details are given for the platinum-manganin bridge-type thermometer. An instrument was needed that could be …

This document is a November 1948 Calorimetry Research Progress Report from the Mound Laboratory. Updates are given in the following areas: (1) development of micro and macrocalorimeters of the resistance-bridge type, (2) study and design of a rod calorimeter, (3) half-life of Postum, (4) evaluation of various calorimeter types, (5) applied mathematics, (6) materials, and (7) future efforts.

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The usual method of producing uranium slugs for the reaction pile is to cast the metal into billets which are extruded into rod about 1.45 inches in diameter. Slugs are then machined from this to the final size of 1.359 inches in diameter by 8 inches long. Extrusion is done in the gamma range at a temperature of about 1000 C, where the metal is soft enough to be extruded at relatively low pressures. This operation is difficult and expensive and the product is not entirely satisfactory. The billets must be protected from oxidation during heating and extruding and the extruded rod must likewise be protected during cooling. Loss of metal due to oxidation is appreciable and a relatively large amount of scrap is produced. The production of dies suitable for use at the high temperatures involved is troublesome. The extruded rod must be straightened before machining and frequently contains stringers of oxide and voids or other internal defects.

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