Abstract: "A dc magnetic mirror machine has been built and tested by the ARC Research Group. Radiofrequency enhancement has been included in the design through the use of rf plates in the vacuum chamber of the machine. For the proton beams of the order of 1[mu]a, the mirror action has been observed as a function of both the rf voltage and the magnitude of the mirror field relative to the main magnetic field. Current measurements were performed with the aid of a Faraday cup with suitable bias grids."

In numerous instances the graphite growth in the older piles has deformed the horizontal control rod holes with a resultant jamming of the rods and overstressing of the rods and thimbles. In addition, special operating procedures to maintain very low differential pressures are required with the present allowed maximum graphite temperatures to prevent collapse of the thimbles because of loss of strength at this temperature. This is currently a limit to the power level of the H Pile. This report discusses a new rod tip and seal which have been developed to allow the removal of the thimble and permit sealing at the pile face. This will allow advantage to be taken of any future increases in maximum graphite temperature with proportional increases in allowable power.

The intent of this manual is to present a description of the main process building, equipment, and auxiliary facilities as well as a process summary. Material is of a scope nature with more detail devoted to features unlike those of existing separations systems. An attempt is made to convey some of the basic design philosophy and the problems encountered in the development of design criteria. This information is written primarily for Separations Section supervision who have not had an opportunity to become conversant with the Purex Project. The manual may also be of assistance in orientation and training of personnel. In order to avoid repetition and duplication of effort, one line service diagrams, equipment sketches, tables, and detailed data are not a part of this manual.

At HAPO the protection of employees from nuclear radiations has paralleled or preceded the emphasis on atomic products production. The production of atomic products on the scale for which HAPO was designed presented voluminous problems in employee education, radiation detection, shielding, and indeed, fundamental research to determine working limits for the various types of radiation exposure which would necessarily be encountered, and to determine working limits for the deposition of radioactive isotopes and mixtures of isotopes in the human body. Since the time radioactive materials first arrived at HAPO and the start-up of the first HAPO reactor on February 23, 1944, there has been a fundamental philosophy that all employee exposure to nuclear radiations should be maintained at a minimum, as opposed to just some level of exposure below the accepted permissible limit. It was with this philosophy in mind that the many achievements and advances in the science of radiation protection at HAPO have been forthcoming. These advances in radiation protection ar discussed in this report.

Letter opinion issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, John Ben Shepperd, regarding a legal question submitted for clarification; Do railroad refunding bonds under submitted facts constitute a novation? Does subparagraph 7 of Sec. 20(a) Chapter 1 of Title 49 of U.S.C. supersede Art. 6257 V.C.S. in any part?

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, John Ben Shepperd, regarding a legal question submitted for clarification: Applicability of the State Prize and Award Tax to the "What's My Name" contest.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, John Ben Shepperd, regarding a legal question submitted for clarification: Authority of the State disaster officials to spray private residences in the Rio Grande flood area.

Abstract: The design and testing of experimental equipment for remotely joining stainless steel tubing by heliarc welding is described. This apparatus consists of a modified heliarc welding torch which is hydraulically controlled to maintain constant arc voltage. A suitable arc voltage sensing and control amplifier circuit was developed for this application.

This report discusses procedures have been established for determining the absolute activities of Sr{sup 90}, Sb{sup 125}, Cs{sup 137}, and gross beta in First Cycle Supernatant. These procedures are also valid for other samples such as scavenged Radioactive Waste (RAW), the primary restriction being that the age of the material be at least 250 days so that any Sr{sup 89} activity (53 day half-life) is negligible. With the exception of the gross beta analysis the results are believed to be accurate to within 10%.

The ability of the atmosphere to disperse and diffuse smoke and gases varies widely with weather conditions. The rate of diffusion is governed mainly by the degree of atmospheric turbulence present. The latter is in itself an extremely complex air motion which acts as the mixing agent in diffusion. This turbulence, which is so fundamental in the diffusion process, depends on such quantities as wind speed, rate of change of wind speed or wind direction with height, and rate of change of air temperature with height. Since these conditions differ widely from hour to hour and day to day, there is a corresponding variation in the diffusing capacity of the atmosphere. The rate of change of temperature with height and the wind speed have the most pronounced effect on the physical appearance of smoke plumes, which in itself provides a clue to the diffusing power of the atmosphere during various atmospheric conditions. The purpose of this note is to present, in semi-technical terms, some of the basic physical concepts related to the behavior of gaseous stack effluents after release into the atmosphere, and to describe certain visible geometrical features of effluent plumes that are directly related to the physical state …

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"A series of thermal neutron diffusion length measurements has been made on non-multiplying lattice of lead-cadmium alloy rods in D2O. One-inch diameter rods in square lattice spacing of 4, 9, 6, 9, and 12 inches were used. Excellent agreement was found between theoretical and experimental values of the diffusion length. The analysis o the diffusion length measurement required a correction for the epithermal neutrons entering the exponential tank. These epithermal neutrons provided a distributed source of thermal neutrons upon slowing down in the lattice."

"A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 degrees F and is returned at 420 degrees F. Steam conditions at the turbine throttle are 600 psig and 825 degrees F. Cost of the complete reactor power plant, consisting of the three reactors, and on 150-megawatt turbogenerator, is estimated to be approximately $43,165,000."

"General Chemistry investigations reported herein includes: (1) the Organic Coolant-Moderator Program, (2) investigations on zirconium hydride, and (3) analytical chemistry."

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Reactor Programs. The design of the Boiling Experimental Reactor is described. The Borax-1 reactor was intentionally destroyed by suddenly adding 4% excess reactivity. Design of the Borax-II reactor is described. It will be used for studies of transient behavior and steadystate operation as a steam producer. A preliminary design configuration has been established in EBR-II employing central, inner, and outer blankets. Fuel geometries including a smaller pin-type element are being investigated. Supporting Design, Research, and Development. The accuracy of diffusion theory for fast reactors was investigated. Water corrosion tests have been performed on high-U alloys, Zr- and Ti-base alloys, and Ni-plated Al plates. Thermal cycling tests were performed on fuel rods and pin-type fuel elements. Results are reported on tests on a current conductor connection for a high-temperature d-c electromagnetic pump, on Na valves with conventional packing, and on a rod-gripper test facility for the EBR-II. A vacuum cup sampler for high-temperature Na and NaK systems is described. Lifting and loading mechanisms for the IBR-II working model are described. (T.R.H.)

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A design study is presented for a sodium cooled, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 deg F and is returned at 420 deg F. Steam conditions at the turbine throttle are 600 psig and 825 deg F. Cost of the complete reactor power plant, consisting of the three reactors and one 150- megawatt turbogenerator, is estimated to be approximately ,165,000. (auth)

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Report presenting two-dimensional aerodynamic lift and moment flutter derivatives for moderate and high angles of attack for several airfoil profiles varying in thickness and thickness distribution. The results indicate that the variables angle of attack, airfoil profile, reduced frequency, and Mach number all have significant interdependent effects.