This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.

Abstract: The Elqui-Vicuna area, Coquimbo province, Chile, was selected for uranium reconnaissance on the basis of two known uranium occurrences and favorable area-wide geologic indications of the possible presence of uranium in commercial quantities.

Abstract: In a study of the comparative importance of sedimentary and tectonic ore controls and in search of data bearing on the origin of the deposits, ten mines in the Lukachukai Mountains, Apache County, Arizona were examined in detail. All commercial deposits in the area are in the Salt Wash Member of the Morrison Formation of Jurassic age. The ore bodies are elongate and horizontally lenticular in shape and consist of one or more ore pockets surrounded or separated by protore. The composite length of ore bodies consisting of two or more ore pockets separated by subore grade material ranges up to 1,100 feet; individual ore pockets range up to 350 feet in length. Elongation is usually at least three times the width and is parallel to paleostream depositional trends measured in and near the ore bodies. Claystone and/or siltstone units nearly always underlie and frequently overlie the host sandstone units. Ore occurs most frequently in trough-type, cross-stratified sandstone which fills scours and channels in the underlying claystone units. Lithofacies maps and mine mapping show that ore bodies are restricted to areas of rapid lateral color change which in general are also areas of rapid change in the ratio of …

From introduction: The purpose of this paper is to give an alternative presentation of the same information presented by the 66 Cartesian graphs of shape perimeter values presented by Rosinski. The 66 graphs have been reduced to 4.

Discussing the potential for Norway to be used as a uranium source.

A report about equipment constructed and methods being explored to determine the effect of irradiation on the thermal and electrical conductivities of encapsulated uranium and on the thermal conductivity of UO2.

In the basic design for a two-fluid LMFRE, a seal has to be made between the metal core inlet and the graphite bottom reflector. To evaluate the effectiveness of such a method of sealing, a screening test apparatus was constructed to determine quickly the physical parameters and the best configuration for interface contact

From abstract: "Calculations are made of the magnitude of the radiation bursts that can occur in a mixer-settler and in a large tank containing U235 solution if the concentration gets out of control. Various rates of increase in concentration are studied and various restraints are imposed on the expansion of the systems. The neutron kinetics equations, with five groups of delayed neutrons, and the equations relating the neutron flux to the pressure and volume of the gas formed by fission fragments are combined into a single first-order nonlinear differential matrix equation which is solved numerically on the IBM 650. In a mixer-settler containing 9.7 kg of U235 the magnitude of the burst was calculated to be about 10^17 fissions, both for low rates of increase in reactivity (<[or equal to]0.01% per sec) regardless of the confinement, and for an unconfined system regardless of the rate of increase reactivity. In a tank containing 88.9 kg of U235 successive bursts of about 10^19 fissions were calculated to occur about 0.5 second apart when the rate of increase in reactivity was about 0.1% per second."

From objectives: "To establish, by literature search, analysis and design, the engineering and fabrication requirements for modifying reactor components and developing and installing the necessary instrumentation to carry out a fuel temperature and flow measurement experimental program."

Results of tests to remove fission gases, xenon and krypton, formed during the operation of a nuclear reactor.

Report issued by the Argonne National Laboratory discussing selected physical properties of various solids, liquids, and gases of interest in nuclear reactor heat transfer and fluid flow analysis. In most cases, values for thermal conductivity specific heat, density, viscosity, and Prandtl numbers are given as functions of temperature. This report includes tables, and illustrations.