Report documenting radioactive fallout across the world, including both material in the atmosphere and that has deposited into food supplies.

Report documenting radioactive fallout across the world, including both material in the atmosphere and that has deposited into food supplies. This appendix includes tables of monthly fallout deposition collections from 116 sites across the Earth and a list of radionuclides and their half-lives.

Annual progress report of safety program for several laboratory divisions.

From abstract: "A previous study of equipment necessary for clean-up following a nuclear accident indicated a need for a portable television system capable of operating in hazardous environments during recovery operations. A system to accomplish this is described and justified in this study."

Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.

Quarterly progress report on a project to test the radiation effects on metallurgy.

Report presenting research and development activities in the field of radioactive wastes. This particular report is concerned with the fixation of radioactive residues when the failure of a pot liner destroyed the furnace.

From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."

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.

From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."

This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.

The purpose of this study was to provide a means for evaluating the various parameters involved in the design and performance of levitation coils.

Report comparing the fuel cycle costs and temperature coefficients of reactivity for PuO2-UO2 fuel in multiple megawatt reactors.

Early results from actual laboratory operation of a more versatile magnet supply.

Report describing investigations to determine the effect of underground disposal of liquid radioactive waste upon the regional groundwater resources.

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

Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II without special components. The SM-1 Core II components were made to specifications very nearly identical to those of SM-1 Core I. The differences consist of europium absorber sections, internal europium flux suppressors in the control rod fuel elements, and low impurity cladding. Each of the SM-1 Core II components with the exception of the five absorber sections new in SM-1 Core I were subjected to a Zero Power Experiment at the Alco Critical Facility. The results of this experiment indicate that the SM-1 Core II will have nuclear characteristics very similar to that of the SM-1 Core I. Since SM-1 Core II will be operated with the same mode of rod control, in the same core support structure, and with the same primary coolant flow conditions, the thermal characteristics should be essentially identical to that of SM-1 Core I. Also, all kinetic characteristics of SM-1 Core II should be identical to those of SM-1 Core I. This report demonstrates that there is no increase in potential for a hazardous situation at SM-1 due to the replacement of SM-1 Core I by …

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

This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.

From abstract: "This report presents an IBM digital computer program that solves numerically and simultaneously the equations that describe gross reactor behavior under runaway conditions."

Summary: Prototype testing of the safety and control rod drives indicated that both units functioned properly. No major problems were encountered during testing. Seal leakage data collected indicated that the seal units were performing satisfactorily. Scram times during both cold and hot testing were excellent and actually better than expected.

From introduction: "The contract covers final design of the SM-2 Nuclear Power (PWR) Steam Electric Station, described in the preliminary design report, APAE 40, Volumes I and II."

Preliminary study to determine the technical and economic feasibility of a 315 eMW High-Temperature, Integral, Liquid Metal Fuel Reactor (HTIR).