Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.

Historical: This process is based on experimental work done in Jackson Laboratory, Send Works, Blue Products, and East Area. It supersedes the Tentative Chambers Works Process for the Manufacture of Fluorine Using Carbon Anode Units, dated December 2, 1943.

Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.

The following report follows an investigation comparing "staggered" and "spit-flow" air cooling systems.

The purpose of the test was to determine the ability of the Control Air System to provide the necessary quantity and quality of clean, dry air to keep the rod drive mechanism stator and position indicator housings at about 3 PSIG in order to avoid low stator resistances resulting from condensation during plant cooldown. The Control Air System is capable of providing the quality of air specified in AEC letter SBO:JWF:100 dated November 17, 1958 of less than 44 grains of moisture per lb. of air in the control air line nearest the reactor chamber.

The general purpose of this report is to present the major characteristics and design of the Consolidated Edison Thorium Reactor (CETR) core

The purpose of the test was to determine the operating conditions of the rod drive mechanisms so that operating personnel may be informed concerning malfunctioning mechanisms. The results the this test favorably agree with previous results. The operating characteristics of the rod drive mechanisms checked in this test have not changed appreciably.

Technical report issued as one of a series of reports concerned with corrosion studies for the Materials Resting Reactor, created to both determine the effect of various practices for fuel plate fabrication on corrosion resistance and to determine the extent of penetration of the fuel plates by localized corrosion attack. [From Introduction]

Abstract: This technical report elucidates principles of hazards evaluation. The concept of hazards potential is introduced and utilized to show how a reactor system perturbation will influence its nuclear safety. Literature relating to reactor safety is referenced to provide the sources of information required for hazards analysis and show how they influence a hazards evaluation. A checklist of items which should be considered in evaluating a change, test, or modification is presented.

This report measures the cross sections of isotopes for 14.5 MeV neutrons and compares the author's results with calculated and existing literature values.

"An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development efforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, Idaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes."

This report seeks to "develop a practical method of evaluating the eddy diffusivity of heat transfer for liquid metals, so that it can be incorporated into the more or less standard theoretical methods to give heat transfer coefficients which are in reasonable agreement with experimental facts"--from introduction.

The following report discusses neutron sources in reactors, discussing general conditions of the study using a flux reactor.

Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.

Research at the University of California Radiation Laboratory has been directed toward the development of processes designed to recover plutonium and uranium from neutron-irradiated uranium. This report has been prepared in answer to requests for information by interested workers in the Atomic Energy programs. The material discussed herein represents the efforts of a sizable research group over several years, and summarizes both the current status of the investigation and the future program now contemplated.

A report discussing exploratory diamond drilling in the Posey and Markey localities.

Technical report with six sections describing the process: (1) The reaction of HN)3 with HSCN; (2) The distribution of nitric acid between hexone and water; (3) The distribution of HSCN between hexone and water; (4) The solubility of thorium sulfate in various extraction solutions; (5) The distribution of protoactinium and fission elements between hexone and aqueous thiocyanate solutions; and (6) Separation of uranium from thorium by extraction into hexone as UO2(SCH)a.

Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.

This technical report details and outlines the BGRR facility's operations and performance record over a period of twelve years. The author of this report finds that the reactor is "one of the most stable and dependable in the business." The report includes two figures.

This report summarizes several reports pertaining to uranium processing.

In connection with different seals for C & D equipment it appears advantageous that many parts could be made of rubber or other elastic polymers. However, data on the deterioration rate of these materials under irradiation are somewhat scant in the available literature. It appears that for neutrons and pure gamma radiation that a good grade of natural rubber stands up best in all the test reported and because the results of the neutron irradiation are so closely correlated with results from gamma it has been proposed that the principal source of damage is caused by secondary irradiation generated within the rubber by the neutrons.

Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).

Geological investigations report of the North Wash Mining distinct of the Henry Mountains in Utah.

This investigation was made to determine whether a diamond drilling program is warranted in the search for ore, and to provide basic data to guide such drilling.