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

A wet collection system for aerosols has been developed using fibrous media. Tests show the performance to be in accord with recently developed theory of collection by fibrous media. The effects of varying aerosol particle size, particle density, and gas velocity have indicated that inertial impaction is the primary collection mechanism. Three-year operating experience on several full scale plant installations shows reliable performance.

A study of the effects of gamma radiation with respect to the formation of nitro-hydrocarbons on the Purex and Redox systems shows that no appreciable formation of nitro-paraffins occurs.

Summary of miscellaneous updates related to the project. This includes information on the following: the declassification of a relevant paper, solubility measurements, static corrosion tests, various other tests involving bismuth, magnesium, uranium, protactinium, and thorium.

An apparatus is described that permits the use of highly ionizing radiations of the Berkeley 60-inch Cyclotron for radiobiological experimentation (ie., deuterons, alpha particles and carbon nuclei).

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"An experiment to determine the effect of reactor irradiation on the thermal conductivity of uranium-impregnated graphite at elevated temperatures as described. The results show a decrease in the thermal conductivity saturating at [approximately] 60 percent at a temperature of 700 degrees C; at [approximately] 50 percent at a temperature of 1000 degrees C; and at [approximately] 25 percent at a temperature of 1300 degrees C. It was found that after irradiation at a given temperature, exposure at a higher temperature resulted in an increase in the thermal conductivity. The converse was also observed. Within the precision of measurement there was no difference in effed between temperature changes produced by varying the fission rate in the samples and changes produced by varying the power in an external heater."

"Continued progress has been made with the high temperature decontamination processes for irradiated uranium fuel. The fused salt treatment of molten uranium has been extended to UCl3. Plutonium and rare earths were extracted into the UCl3 phase. Direct plutonium distillation from molten irradiated uranium has been scaled up to the hundred gram scale. Solid scavenging experiments using uranium oxide, uranium carbide, and uranium nitride in contact with molten uranium have indicated fission product removal. A scaled-up investigation of the separation and recover of uranium from an SIR type ceramic fuel using the volatile fluoride process has indicated the feasibility of this separation method. The effect of irradiation on the decomposition of BrF3 has been further studies in experiments using the NAA statitron.'

"A study has been made of methods to prepare a fluid containing 1 gram of thorium per milliliter. The methods considered were solutions of thorium salts, suspensions of dry solids in water, and collodial suspensions. Thorium oxide, oxalate, and fluoride were tried in conjunction with one or more surface actants, but it was not possible to attain the required thorium concentration. Thorium hydrosol, produced by peptization of thorium hydroxide and subsequent electrodialysis, gave the necessary concentration of 1 gram per milliliter. A solution of 0.5 gram per milliliter was found to be stable to electron irradiation and did not flocculate upon shaking or standing. Selected surface actans which might be used as protective colloids were found to be unstable to electron irradiation.

This technical report summarizes the work which has been done to date on the preparation of magnesium hydride and the attempted preparation of beryllium hydride. Although pure beryllium hydride has not yet been made, the work is continuing, and this report indicates which phases are thought to be worth further work.

The following report presents a preliminary account of the geology and economic aspects of the uranium deposits in the Eureka Gulch area.

The following report studies samples from radioactive deposits in the Hyder district of southeastern Alaska.

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

A report regarding many uranium production plants constructed during the existing emergencies and pressures of World War II that were not intended to be permanent instillations. These plants either contractor or government owned, with buildings on the most part belonging to the contactor and a major portion of the processing equipment belonging to the government, became outmoded with the development

A preliminary report, discussing uranium in the Mayoworth Area in Johnson County, Wyoming

Large savings in waste storage space may be realized by lowering the pH at which TBP waste is stored. Additional savings in neutralizing chemicals and operating time would also increase the monetary gain from such a process change. However, before such a change could be made, the corrosive effect of TBP waste at a lower pH on the mild steel waste storage tanks had to be determined.

A new method of calculating neutron distributions in a cylinder which has appreciable absorption is described. Measurements and calculations on the small-source theory treatment of resonance absorption in U-238 are given. Experimental measurements are reported of the bucklings of lattices utilizing hollow uranium slugs. The effects of varying amounts of cooling water in a graphite-uranium lattice have been measured. A detailed mathematical fitting of experimental reactivity data has been started; some initial results are given here. Curves showing the periods of the lattice testing reactor under various conditions have been calculated in connection with a study of the nuclear safety of this reactor. A method for calculating the critical mass and an estimate (4.4 kg of-U-235) thereof is presented. A technique for measuring the conversion efficiency for U-233 production of Hanford-type lattices is being developed. In connection with the study of the temperature coefficient of reactivity, an analysis has been made of the errors in reactivity change estimates produced by errors in cross-section measurements. The dependence of Pu-240 content in product plutonium on the flux level at which irradiation takes place, which is produced by the 23-day half life of Np-239 is worked out in some detail. An experiment for …

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Reductions in irradiation costs and increases in production rate have provided a continuing incentive for more efficient operation of the Hanford Piles. These improvements have been obtained by means of higher specific powers, greater water flow rates, and better water utilization. However, the extent of the improvements which can be made in this manner may be limited by such factors as tube and slug corrosion, slug stability, and graphite damage rates at higher operating temperatures. Water purification and pumping costs are also factors to be considered. New slug designs are being developed which may be capable of much higher specific power operation. Higher graphite temperatures may also prove feasible, but the water plant performance limitations for the present single pass cooling systems may prove much more expensive to relieve. The use of recirculating cooling water as a means of attaining higher temperature, higher power operation has received preliminary study. A preliminary economic evaluation of an operating area equipped for recirculation versus single pass cooling is needed to better determine the relative merits of the two cooling methods. This report presents the results of such an evaluation and discusses the direction of future development work in the field of pile cooling.

This document presents a summary of work and progress at the Hanford Engineer Works for March 1954. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Service departments have sections presenting their monthly statistics, work, progress, and summaries.

This experiment was designed to furnish data on the quantitative relationship between exposure of enriched uranium metal to thermal neutron bombardment and the subsequent release of gaseous fission fragments from the metal. Studies of data obtained from the in-pile phase of the KAPL Fission Gas Experiment indicate, neglecting startup and shutdown transients, that gaseous fission fragments generated within a 6-mill foil of uranium metal maintained at an operating temperature of about 450 C are released from the foil nearly as fast as they are produced.

This report covers the preliminary data obtained in a metallurgical study of the three enriched uranium slugs which ruptured in the 100-C Pile. The three slugs were from PT-105-532-A2, ``Irradiation of Enriched Uranium Slugs,`` a test conducted by Pile Technology for the purpose of studying the effects of high specific powers in uranium slugs. The uranium used in this test was enriched to 1.75.

This paper briefly reaccounts principal progress items addressed at a April 1954 meeting on ruthenium release and abatement measures for the Redox Plant at the Hanford Engineer Works. (JL)

The C-Reactor is currently equipped with neoprene covered stainless steel bellows connectors between the rear face nozzles and crusaders. These pigtails are failing at an excessive rate and must be replaced at an early date. The replacement design, developed by Pile Technology Sub-Section, utilizes a relatively short length of stainless steel tubing and a slip joint sealed by ``O``-rings. This report describes a test to evaluate the suitability of the slip joint pigtail as a replacement rear face connector.