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

The purpose of this work was (1) to investigate the possibility of producing zirconium-clad zirconium-uranium alloy objects by casting the core alloy directly into zirconium and zirconium-3 w/o tin jackets, producing a diffusion bond at the jacket-core interfaces, and (2) to produce small scale heat thru-put test specimens by this method.

This report describes the manufacture of 25 Aluminum clad, 10 w/o plutonium-aluminum alloy and 5 w/o plutonium-aluminum alloy cored specimens for Argonne National Laboratory-University of California irradiation tests in the Materials Testing Reactor. The manufacturing method: preparation of cores and cladding material, assembly and welding of compacts, outgassing, roll bonding, shearing, identification marking and final fabrication into napkin "rings" is described in detail. Of ninety-six specimens fabricated, ninety-one were completed as finished specimens. Forty-four of these contained 5 w/o plutonium alloy cores and forty-seven contained 10 w/o plutonium alloy cores. Five specimens ere rejected for bond blistering.

A report regarding a field investigation done in 1949, made in order to search for radioactive deposits in the Iliamna Lake-Lake Clark Region, in Southwestern Alaska.

A report regarding radioactivity investigations performed in the vicinity of the Flat, Lower Yukon-Kuskokwim region in Alaska,

A report regarding the geology of the Quartz creek Pegmatite District, in Gunnison County, Colordao

Technical report on the geological investigation of the Green River desert area, Utah, studying uranium deposits in the area.

Discussing the importance to mapping of the Salt-Bluff contacts at King tut Mesa

Studies of ionic entropies in methanol and ammonia have led to the suggestion that ionic entropies in water are abnormally high. An explanation of this hypothesis may be given in terms of entropies of solvation and the high degree of hydrogen bonding in water. When an ion enters water, more disorder is created than when it enters another, less hydrogen-bonded, solvent.

Radioactive decay data are used to calculate the atomic masses of the heavy isotopes, A> 203. The four radioactive families are then connected by means of neutron binding energies known from reactions on various isotopes. Finally all the masses are collectively adjusted for the best fit with mass spectrographic information available in this region. The masses so calculated are presented. Differences between masses of isotopes are estimated to have an of (plus/minus) 0.00020 mas units or about 200 Kev; the position of the masses taken collectively is in doubt by about 1.5 Mev.

Summary of progress on various research projects conducted during January, 1952.

The study was undertaken with the objective of observing the distribution in the rat of organic compounds of phosphorus labelled with the P32 isotope as tracer. The fate of several of these compounds was studied in animals bearing tumors. The distribution of inorganic phosphate in animal tissues is well known but was included in this work for comparison with the organic phosphorus compounds.

The question has arisen of how the beam in A-12 as a long resonant cavity might effect the frequency of operation and the field distribution. This study is published to make available the calculation of the direct beam effect as an illustration of general methods of attacking perturbing effects in resonant cavities.

From abstract: "Two samples, each containing an estimated 10 curies (2 mg) of polonium-210, were purified by vacuum distillation and evaporated onto oblique sections of X-ray targets made of copper. Four lines of the K series and ten lines of the L series of the X-ray spectrum of polonium were recorded with a one-meter transmission crystal spectrograph and a 25-centimeter Bragg spectrograph, respectively. Measured wavelengths agree approximately with values predicted by extrapolation of Moseley's law and with those claimed by Hulubei. Decay of polonium-210 (half life = 138 days) and growth of lead-206 (stable) were observed over a period of 180 days."

From abstract: "This report presents the progress in the laboratory development of a continuous solvent recovery process for the tributyl phosphate-diluent mixture used in the Purex Process. Investigations were made with 1/2" diameter pulse columns, using a nine foot sodium carbonate contacting column and a four foot water wash column."

From abstract: "The following report presents a summary of operating experience with decelerating receivers for ion beam reception. Sample calculations for design of such a receiver for the isotopes of lithium are presented. Estimates of maximum production and requirements to attain such production are given. The maximum ion beam envisioned is 17 amperes obtained from extrapolation of experimental results."

From abstract: "Data obtained in laboratory studies of the 'fumelses dissolving' of irradiated uranium are presented. Procedures for handling dissolver off-gases are proposed."

This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses thorium research, the mechanical properties of metals including thorium, uranium, inconel, and z-nickel, the ANP program (including the following topics: the physical chemistry of liquid metals, and welding research), and the materials testing reactor program.

From summary: "Construction of the HRE facility was essentially complete on November 15, 1951 except for minor revisions and final testing. A program of engineering and nuclear tests of the system hasbeen drawn up, and the tests will be started early in the next quarter. The only major HRE items for which design is not complete are the samplers for the fuel, [gas], and reflector systems. These will be completed in time to be installed before critical experiments begin; meanwhile, temporary sampling devices have been installed for use during the testing program."

This progress report discusses new additions to the Mathematics Panel and discusses new and further work happening at Oak Ridge National Laboratory relating to the Mathematics Panel, of particular note is the Oak Ridge computer which is being fabricated at Argonne National Laboratory and the Technitrol Company.

Final approval of a flow-pressure characteristic curve and orifice pattern for C Pile is desired as soon as possible to allow the completion of orifice assemblies and parallit instrumentation. The presentation of a recommended flow-pressure curve and an orifice pattern has been delayed by a lack of experimental flow data on the C Pile flow system. Discussion with members of the C-431-B working committee and Pile Technology Unit personnel indicated that the use of flows higher than those recommended by the Reactor Unit, in HDC-2327, was desirable on the basis that the costs of supplying more water to C Pile than required by present outlet temperature limits will be small compared to the probable saving that can be made in reduction of corrosion and slug rupture frequency. Using this agreement as well as previous data and the assumption of low enrichment as a basis, a preliminary recommendation of a higher flow curve is presented.

This test project is being carried on for the purpose of testing certain machines which are designed to charge and discharge reactor units with process metal while the unit is in operation. Satisfactory charging of process pieces while the reactor now required for charging operations. These presently required shutdowns are costly in terms of production time, and may cause undesirable thermal stresses in the unit as it changes power level. If charging can be accomplished during operation, reactor shutdowns would only be necessary for maintenance or emergency purposes. During the testing of these metal handling machines, problems have arisen involving the behavior of the process pieces as they are charged. Because these problems directly affect the charging operations, they are being closely investigated also. the machines covered by this report are designated as pressurized machines since they contain the same water pressure as the end of the process tube on ;which they are located. In most of the test work covered by this report, the full scale pressurized charging machine was replaced with a small charging cylinder. The charging operation was simplified by this change.

The Reactor Safeguard Committee formula for the allowable minimum distance between a reactor and the public domain is expressed as: r = 0.01{radical}P, where r = radius from reactor in miles, and P = reactor power level in kilowatts. The six plates in this report illustrates the application of this formula for Hanford Works, both for individual reactors and all reactors in an area.

Estimated water flow rates at H Pile for various postulated conditions are given. The conditions under which the data are valid are as follows: (1) the estimated accuracy of the tube flow rates is {+-}5%, and of pile flow rates {+-}7%; (2) the pile flow rates are based upon the present tube geometry, orifice zone pattern and total flow at H Pile; (3) the flow rates should be increased about 2% if film-free slugs and tubes are considered; and (4) flow rates for enlarged fittings are based upon fittings similar in shape to the present H Pile fittings. The maximum tube flow rates for the DR Pile would be about 2% greater than those given in the table for present tube fittings. For enlarged fittings, the rates for DR Pile tube would be the same as those given for H Pile tubes. The ultimate permissible flow will depend, in part, upon limitations on maximum cross-header pressure and maximum tube inlet pressure, and upon the instrumentation necessary to detect abnormal tube flow conditions.