Report issued by the U.S. Bureau of Mines on its annual safety contest between mine workers. Different types of mines enrolled in the competition and the winners and honorable mentions for 1942 are presented. This report includes tables.

From abstract: "The present report describes experimental work performed to establish a procedure for the production of uranium metal wire. In all cases, the size of the initial rod was 1/2 inch diameter. Three materials were used: hot extruded tuballoy rod, high purity cast tuballoy rod, and cast U-235 rod."

Abstract. Samples of pile graphite, irradiated in a test-hole at Hanford for 15 months, have been assayed for radioactive C14, yielding 0.38 ± 0.04 microcuries per gram. At this level of activity, the pile graphite contains very valuable amounts of C14. The relation between the above assay and the probable average assay of pile graphite is discussed, and it is concluded that the latter is almost certainly above 0.3 uc/ gram. Controlled oxidation of this graphite, either with oxygen at ~ 750°C, or with chromic acid "cleaning solution" at room temperature, yields early fractions which are highly enriched in C14. Concentrations of 5-fold with oxygen, and 50-fold with CRO{sub3}, have been observed. The relation between the observed enrichment and the Wigner effect is discussed, and a mechanism accounting for the observations put forward. According to this, about 25% of the stable carbon atoms in the lattice have been displaced by Wigner effect, a large fraction of which have healed the migrating to crystal edges. All the C14 atoms have been displaced, and the same fraction of these migrate to the edges. The enrichment then results from surface oxidation, in the oxygen case. Predictions are made on the basis of this …

Introduction. the conventional procedures of analysis for uranium and manganese can be employed in the analysis of alloys of these metals. The alloys are reacted with perchloric acid and hydrogen peroxide, fumed to remove any chloride ions, diluted to volume and aliquots analyzed by redoximetry.

Introduction. It has been known for a long time that thorium is precipitated by oxalic acid in acid solutions, but a survey of the literature showed no study of the limits of the acidity and oxalic acid excess which yield quantitative results. V. I. Spitzin reports on the solubility of thorium oxalate in varying concentrations of several acids, but the effect of an excess oxalic acid is not included. Since solutions are sometimes presented for analysis that contain more than the recommended two per cent mineral acid, it would be advantageous to be able to quantitatively remove the thorium without otherwise altering the solutions. This was especially of interest in solutions containing bismuth, since it was hoped that some amounts of thorium could be precipitated in nitric acid solutions containing large quantities of bismuth. In removing the bismuth, first by a bismuth oxychloride precipitation, thee is every opportunity for carrying of the thorium.

Abstract: "A number of direct current conduction type electromagnetic pumps for liquid metals were constructed. Pumping capacities of over 400 gpm and efficiencies of over 50 percent were obtained. NaK alloy at temperatures up to 400 C was used in the test. The large currents required were obtained from rectifiers or from a homopolar generator constructed for the purpose."

"This report gives briefly a rather simple method for fabricating foils from uranium buttons. Two log sheets one of a U-238 run and one of a U-255 run are given."

Summary: "It has been demonstrated that the electrolysis-distillation stages of the procedure that has been developed for traces of metals may be utilized, with certain precautions, to recover milligram quantities of cadmium, cobalt, copper, iron, nickel and zinc. Lead remains partially as undissolved lead sulfate and hence the recovery of amounts ranging from 1 - 5 mg. is not advisable by this procedure."

Updated report about work that originated in February 1942 for the purpose of determining minor amounts of cadmium in uranium and related materials. A method was developed over a long series of studies made following the original report for determining small amounts of various materials in uranium and in a variety of other materials.

This is a progress report on the carbonate process, compiled by the chemical development department of the Carbide and Carbon Chemicals Corporation's Y-12 plant, covering the month of September, 1949. In the previous month, the problem of immediate interest to the Monticello operation were listed. Projects that were left incomplete during that time were continued during this month, as well as a brief investigation of the process in which raw ore is leached with sodium carbonate, the sands and slime separated, the sands leached with acid, and the slimes roasted in a pellitized form.

The following report was made to determine the effective clarity improvement, flow rate characteristics, and operational problems encountered on passing Redox uranium feed solution through sintered, modified Type 304 stainless steel filter elements.

The following report describes and foretells the situation in medium in which neutrons are being (a)produced as fast neutrons, (b) slowed down to thermal speeds by impacts with nuclei, and (c) absorbed by nuclei in such a manner that sometimes fresh fast neutrons appear at the place where a thermal neutron has just appeared.

This report follows a preliminary geophysical investigation that was made in the Colorado-Utah Plateau in search of carnotite ore deposits.

Report and corollary maps on the Eurida (Toh Atin) District, Carrio Uplift, Arizona.

The following report provides a summary of detailed procedures and methods given to small quantities (as low as 0.10 mg) of thorium in rocks and ores.

Technical report describing the purification and separation by distillation of UO2F2 from D2O. In the experiment which is discussed 2,129.6 lbs of UO2F2 were dissolved in 6,605 lbs of D2O. The average isotopic purity of the D2O decreased during the distillation from 99.77% to 99.73%. The dissolved impurities were less than those present originally in the heavy water.

From introduction: The general distribution of known deposits of vanadium-bearing sandstone, which also contain some uranium and radium, is shown in figure 1 1/ and Exhibit A, plate 53. 2/ During 1939-41 the Geological Survey made detailed geological studies of these deposits in the Uravan district, Montrose County, Colorado, as well as preliminary examinations in other parts of the Colorado Plateau vanadium region. In 1942 detailed geological studies were made o the deposits in the Egnar-Slick Rock district, San Miguel Co., Colo.; 3/ the Carrizo Moungains district, Navajo Indian Reservation, Arizona and New Mexico; 4/ the Placerville district, San Miguel County, Colo. 5/ and the Monticello district, San Juan Co., Utah. 6/ Since May 3, 1943, the Gelogical Survey has guided the Bureau of Mines program of prospecting these deposits in parts of Colorado and Utah.

Technical report listing the errata for pages 2, 4, 5, 6, 7, and 8 for report CC-918.

Monthly report of the U.S. Geological Survey's trace element investigations including an outline of field work, laboratory work, and staff activities that have been completed or are in process.

The problem of the separation or enrichment of isotopes is as old as the knowledge of the existence of isotopes of stable elements. The article focuses on the mass-dependent property of atoms continuing to be investigated in laboratories to test its usefulness for new solutions to this problem.

The following report discusses the building design and development of the reactor building, Building 1105, for Argonne National Laboratory, that is meant to house the reactor.

The following report describes the design and construction of the reactor building wing, designed to attach to the reactor building for the Argonne National Laboratory.

Abstract. Thorium peroxide was precipitated from thorium nitrate solutions containing varying amounts of sulfate ion and of hydrogen ion. The washed solids were analyzed both wet and dry. Analyses were made for thorium, peroxide oxygen, sulfate, nitrate, and water contents. X-ray powder photographs of the dried samples by W.H. Zachariasen showed the presence of only two phases. When precipitated from high sulfuric acid, the solid phase was isomorphous with Th(OO)SO4.3H20. More weakly acid solutions whose sulfate content was varied over wide limits [SO4--/Th(IV) (in solution before precipitation) = 0.005 to 67.0] yielded a solid, isomorphous with thorium peroxide nitrate and containing 3.0 to 3.8 peroxide oxygen atoms for each thorium atom. The sulfate content of this latter phase varied continuously between the limits SO4--/Th(IV) = 0.34 to 0.01 with nitrate ion present when the sulfate content was very low. This continuous variation in composition is in agreement with the previously proposed structure of this phase.

The following report studies a method of assay where an unknown sample is determined by comparison with a standard sample of known isotopic ratio. The purpose is to acquaint the technical personnel with the fundamentals of the feedback method of assaying samples of TF6.