Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.

From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.

Annual progress report of safety program for several laboratory divisions.

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.

Report describing an "investigation of steady-state counter-flow of gases in a large pore graphite" by exposing it to streams of helium and argon.

An engineering-scale demonstration of the Sulfex process indicated that semi-continuous decladding of unirradiated stainless steel-clad UO2 or U02ThO2 fuels is feasible.

Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.

Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.

Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.

Second volume of a compilation of information about reactor containment, written by experts from a variety of organizations.

From foreword: "Summarizes current practice in the subject of secondary shutdown systems and evaluates the capabilities of the secondary shutdown systems that were examined."

First volume of a compilation of information about reactor containment, written by experts from a variety of organizations.

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."

From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."

From introduction: "Cytological examinations of the irradiated and some unirradiated populations in the radioactive sediments of White Oak Creek and the Clinch River were made."

Report describing a set of high-precision routines for the IBM 7090 that perform efficiently the calculations most often required on axially symmetric magnetic systems. The routines compute the vector potential, field components, and the mixed gradient for current systems and for certain idealized distributions of magnetized matter. The programs for the current systems were developed from a set of six equations in elliptic integrals, which suffice when correlations are fully exploited for all the relevant properties of loops and solenoids.

Report containing the ongoing research and developments of the Oak Ridge National Laboratory's Reactor Chemistry Division.

From Introduction: "The present semiannual progress report introduces more active consideration than has been given in the past (by us, at least) to the importance of energy degradation in DCX-like devices. The following pages introduce also a new major apparatus designated as DCX-2. Some of these concepts cannot as yet be released publicly and therefore Chap. 3 of this report, covering the DCX-EP-B design, is being issued separately, with restricted distribution, as ORNL-3044."

Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.

Results of processing 47 metric tons of Brookhaven spent reactor fuel are summarized.