11,400 KW Nuclear Power Plant Employing an Organic Moderated Reactor: Preliminary Description (open access)

11,400 KW Nuclear Power Plant Employing an Organic Moderated Reactor: Preliminary Description

Abstract: The preliminary design is described for a small electric-power-generating plant powered by an organic moderated reactor. System and component requirements are discussed and possible design configurations and equipment are described.
Date: 1957
Creator: Wheelock, C. W.
System: The UNT Digital Library
Basic Chemistry of High Temperature Inorganic Systems, Semiannual Progress Report: July-December 1956 (open access)

Basic Chemistry of High Temperature Inorganic Systems, Semiannual Progress Report: July-December 1956

From abstract: The vapor pressure determination of solid ThF4 has been completed. Experiments to determine the heat of formation of ThF4 by studying the reaction of ThF4 with SiO2 are described.
Date: July 15, 1957
Creator: Yosim, S. J. & Milne, T. A.
System: The UNT Digital Library
KEWB Program Quarterly Progress Report: July-September 1956 (open access)

KEWB Program Quarterly Progress Report: July-September 1956

From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.
Date: March 1, 1957
Creator: North American Aviation. Atomics International Division. Kinetic Experiments on Water Boilers Program.
System: The UNT Digital Library
Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956 (open access)

Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956

Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the first report of the series and coves the period from the initiation of the project to July 31, 1956. Also included as an appendix to the report is a detailed description of the OMRE facility" (p. 3).
Date: March 15, 1957
Creator: Trilling, C. A.
System: The UNT Digital Library
Reactor Safety Quarterly Progress Report: May-July 1956 (open access)

Reactor Safety Quarterly Progress Report: May-July 1956

From abstract: Impact tests on the Mark III Hanford safety element indicate that the design is mechanically adequate and does not constitute a personnel hazard.
Date: March 15, 1957
Creator: Miller, N. C.
System: The UNT Digital Library
Sodium Reactor Experiment Pump Development (open access)

Sodium Reactor Experiment Pump Development

Design and operational techniques are described for a freeze seal type centifugal pump for use in the Sodium Reactor Experiment.
Date: January 1, 1957
Creator: Cygan, R.
System: The UNT Digital Library
An Evaluation of the Calder Hall Type of Nuclear Power Plant (open access)

An Evaluation of the Calder Hall Type of Nuclear Power Plant

Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
Date: January 18, 1957
Creator: Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
System: The UNT Digital Library
Reference Design for an OMR-Powered 38,000-DWT Tanker (open access)

Reference Design for an OMR-Powered 38,000-DWT Tanker

Abstract: This report presents a reference design of an organic moderated and cooled reactor for the propulsion of a 38,000-dwt tanker.
Date: March 18, 1957
Creator: Gimera, R. J. & Stanbridge, R. E.
System: The UNT Digital Library
A Further Evaluation of the Calder Hall Type of Nuclear Power Plant (open access)

A Further Evaluation of the Calder Hall Type of Nuclear Power Plant

Abstract: This report presents the results of plant optimization studies and cost estimates of the reference design for a natural uranium, graphite moderated, gas-cooled reactor and power plant which was described in NAA-SR-1833.
Date: June 28, 1957
Creator: Banks, William F.
System: The UNT Digital Library
Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel (open access)

Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel

Abstract: The data presented herein, in the form of graphs, can be used to obtain the value of this energy.
Date: November 15, 1957
Creator: Ashley, R. L.
System: The UNT Digital Library
Organic Moderated Reactor Experiment Progress Report: August-October 1956 (open access)

Organic Moderated Reactor Experiment Progress Report: August-October 1956

Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the second report of the series, and covers the period from August 1, 1956 through October 31, 1956" (p. 3).
Date: November 15, 1957
Creator: Trilling, C. A.
System: The UNT Digital Library