From introduction: This report summarizes some of the results of U. S. Geological Survey investigations in the Club Mesa area and presents a compilation of available geologic data that would be helpful in future exploration. Detailed geologic logs of U. S. Geological Survey holes drilled in the Club Mesa area on public land that is no longer withdrawn from mineral entry are on open file for public inspection in the U. S. Geological Survey office, Grand Junction, Colorado.

Memorandum presenting a study of the performance of swirl-can combustor elements for an experimental short-length turbojet combustor utilizing hydrogen fuel at high-altitude operating conditions. Fuel was injected into each element through a tangential, sonic orifice that created a swirling fuel-air mixture within each element. Results regarding combustor blowout, combustion efficiency, outlet temperature distribution, and preliminary performance of multielement combustor are provided.

An engineering flowsheet has been prepared for the conversion of an aqueous slurry of cesium-zinc-ferrocyanide into a dry cesium chloride product by the calcination process. Flowsheet No. 1 defines a six-step batch-type calcination operation for processing the slurry into a dry powder for offsite shipment in bulk containers. Some of the advantages to this process are as follows: Product losses are expected to be small, estimated to be less than 0.03 percent; the equipment required to process a given number of curies per batch appears to be relatively small, compact, and simple; the process does not impose severe requirements for materials of construction; and requirements for process control and instrumentation are expected to be simple. There are two disadvantages to this process. First, the cesium-zinc-ferrocyanide precipitate is not considered economically filterable, hence, the separation of solids from liquids is encumbered. Second, the process, as outlined, if potentially hazardous because of the possible nitrate carry-over with the influent slurry. This nitrate may cause a rapid reaction in the calcination step. It is concluded that this flowsheet offers a satisfactory scheme for isolating radiocesium if the process is modified to preclude the possibility of nitrates or other unwanted oxidants from reaching the …

From abstract: " The interaction of positive K mesons having energies between 20 to 220 Mev with the nuclei of photographic emulsion has been investigated."

The following report describes a gaseous scintillation counting system, including the production and operation of the counter.

From abstract: "This bibliography consists of reports compiled from the AEC Library Card Catalog. Only the Classified and Unclassified report literature is included. For the published literature the reader is referred to an unpublished paper by V. Carson (UCRL - Livermore Library)" titled "Radioactive Waste Disposal" (April 25, 1957). "All progress reports covering the work have been omitted in order to exclude a large amount of duplicate information which is usually found in more detail in topical reports."

The following report investigates the cohesive energy of ionic crystal lattices in the alkali halides when at a high pressure.

Report discussing a study regarding the measurement of surface acceleration following the detonation of an underground charge at the USGS Tunnel.

Since the installation of Ball 3X equipment on the older reactors, several inadvertent ball drops have been experienced, many of which have required considerable recovery time. Furthermore, it is very probable that these recovery times be significantly increased subsequent to the proposed installation of air accelerated vertical safety rods. Because of this, interest has been expressed by reactor operations personnel toward provision of a ball recovery system which would substantially reduce these outages.

This document details activities of the irradiation processing department during the month of April 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: research and engineering operations; production and reactor operations; facilities engineering operation; employee relations operation; and financial operation.

The purpose of this report is to summarize all actual and potential power level limits under which the K Reactors may be forced to operate during the next year. In addition, a summary of the methods being followed to eliminate each is to be discussed along with a graphical presentation of the relationship of the various limits. For the purpose of this report, it was assumed that all power levels will be attainable from a physics aspect since these problems are discussed elsewhere. It is not the intent of this report to recommend that these power levels be attained but only to indicate what production levels are possible through operation on any one limit. Seven outlet temperature limits govern operation at the K Reactors. They are: TBI Limit; Crosstie Limit; Rear Header Saturation Limit; Bulk Outlet Temperature Limit; Tube Corrosion Limit; Temperature Monitor Limit; and Rupture Control Point. Operation during the summer months of 1957 will require cuts in power in order to remain within these limits unless modes of circumventing a few are found. The limits are shown graphically in the appendix at the various flow rates probable. From these curves it is evident that the Low Trip TBI …

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This report addresses the summary report of the Chemical Engineering Division.

Current Panellit protection procedures, termed instability limits, come from calculations based on steady state experiments. However, the actual conditions in a process tube following a plugging occurrence sufficient to cause unstable flow are transient rather than steady state, and cannot be determined with great precision except by transient state experimentation. As a result, a program was initiated by the thermal Hydraulics Operation of HLO to perform a series of transient heat transfer experiments which would define the process tube response to (1) rapid plugging in the process tube assembly, (2) slow plugging in the process tube assembly, and (3) power excursions above normal of varying amounts. Transient heat transfer experimentation on a large scale is not common and many difficulties have been encountered. After preliminary runs were made and reported, a further series of runs were planned and run which would include K as well as BDF type data and would define more closely the upper limit of the panellit protection. During the test runs, data from these transient experiments are recorded on high speed recording instruments, each of which has a calibration which is subject to change regardless of the efforts expended by the experimenters. This means that checking …

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Results of a study to compare economic factors of of burner- versus breeder-type liquid metal fuel reactors. The study takes into account several pertinent criteria and factors to ensure that the reactors would be reasonable to implement.

Abstract: "Two transistor plug-in decade counters are described, one of which operates over the SCS-7 temperature range. A transistor digital scanner with storage and parallel readout is described. It utilizes one of the plug-in decades. A simple design procedure for flip-flops is presented."

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Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cent of UC, U/sub 2/Ti, U/sub 3/Si, or U/sub 6/Ni dispersed in Zircaloy 2 and 30 volume per cent of UC or UN dispersed in Type 18-8 stainless steel have been investigated. Roll-clad plate-type elements of all these compositions may be fabricated by powdermetallurgy methods in such a manner that good core-tocladding bonds and cores with uniform dispersions of discrete uranium- compound particles are obtained. From the standpoint of fabricability, elements containing UC in Zircaloy 2, UC in stainless steel, and UN in stainless steel are the most promising. The UN in stainless steel has the best corrosion resistance in 680 deg F degassed water; however, UC in stainless steel has the best resistance to corrosion in 700 deg F NaK. (auth)

The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabilization of the gamma phases. The U/ sub 3/Si alloy, on the other hand, suffered severe deterioration, particularly of corrosion resistance. Changes in electrical resistivity, hardness, mechanical properties, and crystal structure are presented and the mechanisms producing the observed changes discussed. (auth)

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