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]

This report discusses properties and data regarding the neutralized and concentrated aqueous waste produced during studies of the tributyl phosphate (TBP) solvent extraction process.

Report discussing an experiment in which the formal potentials of the Pu(III)-Pu(IV) couple in 1M perchloric acid and in 1M hydrochloric acid are determined. The potentials were measured through potentiometric titrations of Pu(III).

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

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.

The use of thermally fissionable material in the lattice adds a distributed source of fast neutrons which must be considered in evaluating the problem.

Tests made on the Oy-Tu reacting assembly at Pajarito indicate that the lateral displacement of two halves of the active material within the assembly can be used as a control mechanism on this type of reacting assembly. This report describes a reacting assembly using a rotary control mechanism based on this principle and indicates the sensitivity of control possible with such a device.