A Pebble-Bed Reactor for Stationary Power Plants (open access)

A Pebble-Bed Reactor for Stationary Power Plants

A preliminary study has been made of a solid homogeneous reactor for stationary power plant application. The core consists of graphite spheres impregnated with uranium and thorium, and the coolant is bismuth. This concept possible offers advantages over other solid fuel reactor systems with respect to simplification of core structure, fuel fabrication and fuel handling, and reduction of fuel inventory external to the reactor. From the results of this preliminary study, it appears that the potential cost of electric power from this reactor is competitive with that from other reactor systems which have been proposed for the same application. The Po210 produced in the coolant presents a decontamination problem, but is also possibly a valuable by-producgt.
Date: May 15, 1954
Creator: Beeley, R. J.
System: The UNT Digital Library
Radiation Effects, Quarterly Progress Report, January-March 1954 (open access)

Radiation Effects, Quarterly Progress Report, January-March 1954

None
Date: May 24, 1954
Creator: Faris, F. E.
System: The UNT Digital Library
Radiation Effects, Quarterly Progress Report, October-December 1953 (open access)

Radiation Effects, Quarterly Progress Report, October-December 1953

None
Date: May 15, 1954
Creator: Faris, F. E.
System: The UNT Digital Library
SRE Instrumentation and Control (open access)

SRE Instrumentation and Control

Introduction: This memo gives a general description of the components and equipment affecting the control of the SRE, and the equipment associated with all reactor services.
Date: May 21, 1956
Creator: Hall, R. J.
System: The UNT Digital Library
Reactor Physics, Quarterly Progress Report, November, 1953 - January 1954 (open access)

Reactor Physics, Quarterly Progress Report, November, 1953 - January 1954

"A series of thermal neutron diffusion length measurements has been made on non-multiplying lattice of lead-cadmium alloy rods in D2O. One-inch diameter rods in square lattice spacing of 4, 9, 6, 9, and 12 inches were used. Excellent agreement was found between theoretical and experimental values of the diffusion length. The analysis o the diffusion length measurement required a correction for the epithermal neutrons entering the exponential tank. These epithermal neutrons provided a distributed source of thermal neutrons upon slowing down in the lattice."
Date: May 15, 1954
Creator: Laubenstein, R. A.
System: The UNT Digital Library
Maritime Organic Moderated and Cooled Reactor (open access)

Maritime Organic Moderated and Cooled Reactor

Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.
Date: May 27, 1959
Creator: unknown
System: The UNT Digital Library