A survey and analysis of the potential opportunity for the use of nuclear reactors to satisfy process and space heat requirements in the continental United States and Alaska has been completed. The greatest emphasis has been devoted to manufacturing industries that utilize large quantities of process heat.

Abstract: In 1958 geologists of the U.S. Atomic Energy Commission and the Instituto de Investigaciones Geológicas de Chile made a reconnaissance for uranium in the Mamiña area, Province of Tarapacá in northern Chile.

Introduction: This exploratory work was undertaken as a preliminary evaluation of the area's uranium potential, and was limited to reconnaissance for favorable geologic indications of uranium, which included visits to selected localities and mining districts.

The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).

A report about thermal-conductivity and electrical-resistivity measurements made on a uranium-1.5 w/o zirconium alloy surrounded by NaK enclosed in a Zircaloy-2 capsule which were in poor agreement with measurements made directly on a uranium-1.5 w/o zirconium specimen.

From abstract: Report of commercial buildings exposed to a nuclear device detonation.

From Abstract: "Fuel tubes of enriched uranium-aluminum alloy were melted to various degrees of severity in the SPERT I reactor as a part of a program to evaluate reactor operating hazards. The heat flux encountered during the tests ranged from 200,000 to 650,000 pcu/(hr)(ft^2). The time required for the metal temperature to reach the melting point from the time when burnout began varied from 1.3 to 4.9 seconds. During these tests, pressure pulses were produced at a frequency of about one per second with peaks of about 150 psi."

Phase I - Plant Transient Analysis. Behavior of the basic and refined kinetic models differs only slightly. It is therefore suggested that the basic model be used in any studies where the improvement in fidelity attainable fro the refined model is not warranted by the complexities introduced by the addition of function generator to the analog circuitry and derivation of the function to be programmed. The parameter responses of both kinetic models appear to be essentially similar to those of the plant with the exception of the primary pressure. In the pressurizer analysis it was noted that the primary system pressure surges of the model should be higher than those of the plant because of the adiabatic steam compression assumed in the model derivation. the fact that the mode surge is very much greater indicates that the compression process is far from adiabatic. A more detailed and complex model of the pressurizer, one that evaluates heat transfer in the steam pocket boundaries, would therefore reduce the costly conservatism otherwise necessary in the specification of pressurizer vessel size. Phase II - Xenon Reactivity Transients. On the basis of this study an analog computer circuit has been presented which accurately represents bank …

Discussing a drilling program planned to investigate the lithology and internal stratigraphy of the Wasatch formation and to determine the depth to the underlying surface of unconformity of the basal contact of the Wasatch formation.

Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment.

Liquid Metal Fuel Reactor Experiment program quarterly technical report.

Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).

Discussing an investigation made to search for the evidence of channels for hydrothermal uraniferous solutions in the diatremes of the Hopi Buttes volcanic field.

A report regarding regional fracture systems mapped for an area of about 90,000 square miles, embracing most of the Colorado Plateau and small strips of the adjoining Rocky Mountains, by the use of aerial photographs and mosaics. The data interpreted from the photographically reduced to produce the final map.

Geologic map of the Crooks Map District, Freemont District, Wyoming showing core drill holes prepared for a report by U.S. Atomic Energy Commission, Grand Junction Office.