Abstract: Two 20-foot-long, 7-foot-diameter, 10-gauge structural-plate pipes having longitudinal joints with 8 bolts per foot were buried and tested in the Smoky event of operation Plumbob at nominal predicted pressure levels of approximately 170 and 195 psi.

The APPR-1 is a pressurized water reactor having a low specific heat fuel and a water primary coolant. The primary coolant loop delivers heat from the reactor to the steam generator. The secondary water in the steam generator is converted to steam and then taken to the turbine to drive an electrical generator. The simulation of this system is broken down into three primary areas: the neutron kinetics in the reactor which are necessary to generate the primary power function, the heat transfer in the reactor, and the heat transfer in the steam generator.

This is a sample operating manual designed to aid experimenters in writing operating manuals for MTR and ETR experiments. It contains what is felt to be the necessary information for operating a particular experiment. One of the main functions of an operating manual is to provide quick reference to material needed in an emergency. It is believed this type of manual provides the required information without an excessive amount of bulky, surplus material.

Graphs for estimation of plutonium and trans-plutonium isotopic content of irradiated plutonium reactor fuel of various initial isotopic compositions.

Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.

From abstract: The design parameters for the various KE-ACF designs are outlined and a summary of the design features to be covered in detail at this symposium is presented.

From abstract: A team consisting of R. A. Lindblom, S. A. Mayer, R. G. Young, W. L. Chenoweth, R. F. Droullard, and I. T. Fisk made a reexamination of the Anderson mine (Uranium Aire) of Interstate Oil and Development located near Wickenberg in Yavapai County, Arizona. The field examination was made from August 22, 1958 to September 2, 1958. This team was formed to resolve differences between company and AEC ore reserve estimates. A cooperative effort in which the company supplied labor, limited additional drilling and both parties were in attendance during the sampling resulted in the collection of additional data. Special attention was given to assessing the in-hole assaying with radiometric equipment by IOD and AEC, evaluation of tonnage factors, moisture content, continuity of ore, and current mapping of stripped and mined areas.

From abstract: "A preliminary design is presented for a boiling water reactor power plant for a propulsion of a 22,000 SHP commercial tanker."

Abstract: This report outlines the general techniques developed for replacement of PRE in-cell equipment or equipment components.

Reporting investigations into the lithologic and structural ore controls as revealed by this exploration program.

Report that offers updated information from the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) "experiment safety circuit manual by providing ETR power reduction curves and other information on ETR not yet available at the time the manual was issued, September 15, 1957" (p. 1).

Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.

Abstract: During March 1958, representatives of the health and Safety Laboratory, New York Operations Office, visited Columbia University to make stray radiation measurement at the Van de Graff accelerator. A radiation survey was performed at the Van de Graaff electrostatic generator at Columbia University. The survey results do not indicate a particular need for additional shielding at this time. It is recommended that the analyzer area of the beam room should not be occupied during beam operations and the present interlock system should be modified by the installation of a photocell interlock as shown on the included plan.

Progress report discussing projects and work completed by the University of Michigan Department of Chemistry 1957-1958.

A report pertaining to the thermal-conductivity and electrical-resistivity measurements of uranium encapsulated in zircaloy-2 and surrounded with NaK as a heat-transfer material which is not in agreement with results obtained from unclad uranium.

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

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.

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.

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).

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).

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.

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."

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

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