1024 Channel Time-of-Flight Analyzer for MTR Fast Chopper - Operating Manual (open access)

1024 Channel Time-of-Flight Analyzer for MTR Fast Chopper - Operating Manual

Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.
Date: March 11, 1959
Creator: Petree, F. L.
System: The UNT Digital Library
Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho, Part 3: Hydrology and Water Resources (open access)

Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho, Part 3: Hydrology and Water Resources

This report describes the hydrology and evaluates the water resources of the ERTS, sets these in their regional perspective, and forecasts conditions and effects during future years.
Date: 1959
Creator: Nace, Raymond L.; Deutsch, Morris; Voegeli, Paul T.; Steward, J. W.; Walton, William Clarence; Fowler, K. H. et al.
System: The UNT Digital Library
Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant (open access)

Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date: September 30, 1959
Creator: Linenberger, G. A.
System: The UNT Digital Library
In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T) (open access)

In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
System: The UNT Digital Library
Heat Transfer in an Annulus with Asymmetric Heating (open access)

Heat Transfer in an Annulus with Asymmetric Heating

Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
Date: February 1959
Creator: Lisin, Alexander Vladimir; Mackewicz, W. V. & Reynolds, William C., 1933-2004
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959 (open access)

Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date: May 25, 1959
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Oak Ridge Site Report 30,000 KiloWatt Prototype Partially Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant (open access)

Oak Ridge Site Report 30,000 KiloWatt Prototype Partially Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant

From introduction: "This report describes the selected site for a prototype nuclear plant, the reactor safety aspects for the site, the modified design of the plant, and estimate of the design and construction cost."
Date: March 1959
Creator: Kaiser Engineers
System: The UNT Digital Library
Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office (open access)

Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office

Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.
Date: March 1959
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
System: The UNT Digital Library
Design Bases for ICPP Waste Calcination Facility (open access)

Design Bases for ICPP Waste Calcination Facility

Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).
Date: January 16, 1959
Creator: MacQueen, D. K. & Stevens, J. I.
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1959 (open access)

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1959

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
Date: July 31, 1959
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Experimental Organic Cooled Reactor : Conceptual Design (open access)

Experimental Organic Cooled Reactor : Conceptual Design

Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.
Date: December 1, 1959
Creator: Huffman, John R.; Nyer, W. E. & Rainwater, J. H.
System: The UNT Digital Library
Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype of an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office contract no. AT(10-1)-925 (open access)

Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype of an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office contract no. AT(10-1)-925

Report containing the preliminary design for a nuclear reactor plant and its facilities. Includes a description of systems, safety procedures, costs, and a glossary.
Date: March 1959
Creator: Kaiser Engineers
System: The UNT Digital Library
Appendix to Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission Idaho Operations Office Contract No. AT(10-1)-925 (open access)

Appendix to Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission Idaho Operations Office Contract No. AT(10-1)-925

Report containing outlines of operating procedures, costs, construction, safety analysis, studies, and design specifications of a 30,000 kilowatt prototype partially enriched uranium nuclear power plant.
Date: March 1959
Creator: Kaiser Engineers
System: The UNT Digital Library