Monthly magazine discussing natural resources, parks, hunting and fishing, and other information related to the outdoors in Texas.

A preliminary mathematical study is made of the maximum expected expansion of barium titanate ceramic. It is noted that there is insufficient physical evidence for a complete answer and some possible mathematical models are discussed and compared.

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

The flux through a given region is proportional to the total lengths of the neutron flight paths that intersect that region. The analytical Monte Carlo procedure manufactured neutron flight paths and totaled the lengths of all paths intercepted by the regions illustrated in Figure 1. The procedure was designed to utilize the various symmetries in the lattice. / Consider a portion of the lattice whose planar cross-section is shown in Figure 5. If R is the region in which the flux is to be estimated and F the fuel rod in which the neutron originated, then flight path P results in an intercepted length whose reflection in the plane is L. On the other hand flight path P' intercepts R' with length L'. R' is not the region to be studied, but a translation of the flight path P' to F' would result in the neutron intercepting R. The origin in P was arbitrary. For each neutron originating in P another could, with equal probability, have originated in P' with parallel paths. Hence consulting L' in R' towards the total flux is equivalent to starting a neutron at P'. Thus consideration of all regions symmetric to R with respect to …

The Spectroscopy Research Laboratory is concerned with research and development in the fields of nuclear magnetic resonance, microwaves, infrared and optical spectroscopy, spectrochemistry, and x rays. Research is directed toward fruitful methods of isotope analysis; new element and compound analytical methods having application to immediate Laboratory or long-range commission needs; and fundamental research on isotopes, elements, and compounds. The work is reported on a project basis to give a more complete picture of the purpose, activity, and status of each program. More detailed information on reported or inactive projects may be obtained from the previous semiannual report.

Specifications for the proposed in-pile loop to be placed in the Hanford Reactor. The the purpose of the proposed installation of an irradiation facility accounting to a high pressure, high temperature recirculating loop for the Westinghouse Atomic Power Division (WAPD) is to test the integrity of fuel specimens. This report, in support of the feasibility study, cost estimates, and schedule, presents design specifications for the loop.

Production Test 313-105-13-M authorized the irradiation of a uranium - 0.4 atomic per cent chromium alloy to determine the relative stability of this material during irradiation. Five tubes, each containing six four-inch alloy slugs, were irradiated to exposures ranging from 156 to 834 MWD/T. This report describes the results of the visual examination of the bare uranium alloy slugs and the results of the test to determine slug breaking strength. The breaking strength of both the U-Cr alloy slugs and the normal uranium control slugs was reduced by exposure in the pile. The breaking strength of those U-Cr alloy pieces not cracked or broken in the jackets before examination was consistently greater than the breaking strength of the normal uranium at all exposures.

In connection with the development of in-line analytical equipment for monitoring pH, gamma activity and uranium concentration in process streams, experiments and tests were carried out during the past year and a half in the Metal recovery Plant on a pH monitor for the hydrogen ion concentration in neutralized waste, a continuous gamma activity monitor on the RCU, an automatic photometer for uranium in RAF, and an automatic polarograph for uranium in RAW. This letter is written to present up-to-date diagrams of the equipment used, outline briefly the studies conducted and the main conclusions regarding design and operability of the equipment, and present material which will supplement that included in the previous reports on theses instruments.

The four types of respirator cartridges used at the 202 S Building were tested against aerosols found at that location, and in the laboratory against non-radioactive gaseous ruthenium tetroxide. Positive penetration of two types of cartridges was shown with one process aerosol. Gaseous ruthenium tetroxide penetrated all types of cartridges tested. Leaks were found in some of the cartridges. Particle size of aerosol particles was measured by means of cascade impactor samples and electron photomicrographs. A high percentage of the aerosol particles was found to be less than 0.2 microns in diameter. Ru¹⁰³ + Ru¹⁰⁶ and Zr⁹⁵ + Nb⁹⁵ were shown to be present in the process aerosol by gamma ray spectrometer analysis. Possible causes of penetration of respiratory equipment by ruthenium are discussed and suggestions made for alleviating the problem.

A production test composed of preformed zirconium samples was prepared by R. S. Kemper of the Physical Metallurgy Unit⁽¹⁾ to determine the effect of exposure time and the influence of prior mechanical cold work on changes occuring [sic.] during irradiation. The first section was delivered to Radiometallurgy Unit is April, 1954, for examination after an exposure of 190 MWD/AT.

A plutonium solution of known Pu-241 content was purified by solvent extraction techniques to remove uranium and americium impurities. Portions of this purified solution were then analyzed for U-237 as a function of time. Since the growth of U-237 occurs directly by the alpha decay of Pu-241, these measurements provided sufficient data for calculation of the Pu-241 alpha half-life, which was found to be 2.91 ± 0.50 x 10⁵ years.

A class of critical assemblies has been considered in which the core consists of an oralloy bearing gas at more or less standard pressure and temperature and the reflector is an efficient moderator with a small thermal capture cross section. Age and diffusion theory have been applied to compute the probability that a fast neutron is thermalized by the reflector and them captured by the core. It is first assumed that fast or epithermal neutrons do not interact wit the core and it is later shown that this assumption should be a good one for many cases. The reflector may be a thick spherical shell. It is shown that oralloy masses of a few kilograms can be critical within thick reflectors of D2O, Be, C or combinations thereof. Curves are attached which enable one to estimate critical configurations.

A report regarding the geology of the Thomas Range Fluorite District, in Juab County, Utah. This report concerns work done on behalf of the Division of Raw Materials of the U.S. Atomic Energy Commission.

A report regarding a reconnaissance for radioactive deposits in southeastern Alaska, 1952. Concerns work done on behalf of the Division of Raw Materials of the U.S. Atomic Energy Commission.

An Interim report regarding exploration in the Yellow Cat area, Thompson district, Grand County, Utah. Concerns work done on behalf of the Division of Raw Materials of the U.S. Atomic Energy Commission.

This report summarizes the results of this exploration and outlines the general plan for additional exploration, all of which is being done on behalf of the division of raw Materials of the US Atomic Energy Commission.

From abstract: "An instrument capable of detecting fission-product contamination in the moderator has been developed. It consists of a thin-walled ion chamber and associated electronic equipment for automatically detecting deviations from normal moderator decay rate. Indication of fission-product activity is independent of power level, flowrate, and other ambient conditions. Tests show the sensitivity and long-term stability to be good."

Report outlining the relation of the ASTM flash point of oil, a rough measure of the safety of storage and use when oil sparks, to other directly determinable physical properties. Summarizes the data on vapor pressures, boiling curves, and flash points of various hydrocarbon diluents.

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W. J. O`Leary and R. R. Herries visited BMI to review the progress of subcontract research on extended surface fuel elements and on consolidation of Horizons` thorium. 1. Corrosion samples, 1in. diameter {times} 0.180in. thick nickel-plated uranium, which had been press-clad with aluminum at 510{degree}C and 6000 psi, have been on test for 18 days with no evidence of undercutting. Similar samples press-clad with 10,000 psi have been exposed for 7 days with no failures. 2. The hydrogen and chlorine content of as-received Horizons` electrolytic thorium was greatly reduced during vacuum sintering and arc melting. 3. A second lot of Horizons` thorium has been compacted and sintered to provide electrodes for two 9-10 lb. melts. 4. Diffusion couples are being annealed and examined in order to determine the rate of solid solution diffusion of thorium in aluminum.

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W. J. O`Leary and R. R. Herries visited BMI to review the progress of subcontract research on extended surface fuel elements and on the consolidation of thorium powder. 1. Seven electrodes of Horizons` powder have been pressed and satisfactorily arc melted under various conditions. 2. A second lot of 18 to 20 lbs. of Horizons` metal has been received at BMI for melting. 3. Eighteen of the proposed 33 ``half-dollar`` uranium corrosion samples for investigation of higher bonding pressures have been prepared. Ten of these are on test in boiling distilled water. 4. Three ERL fluid-pressure-bonded uranium corrosion samples failed due to sheath rupture after 31-33 days on test; no ``undercutting`` was evident. These samples have shown satisfactory corrosion resistance.

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