A Multichannel Digital Recording System (open access)

A Multichannel Digital Recording System

Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date: September 15, 1960
Creator: Truitt, R. W.
System: The UNT Digital Library
Steam-Cooled Power Reactor Evaluation: Graphite-Moderated, Boiling Water, Steam-Superheat Reactor (open access)

Steam-Cooled Power Reactor Evaluation: Graphite-Moderated, Boiling Water, Steam-Superheat Reactor

Abstract: A conceptual reference design of a 318 Mw(e) Graphite Moderated Boiling and Superheating Reactor (GBSR) is described.
Date: September 1961
Creator: unknown
System: The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964 (open access)

Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964

From introduction: This report provides industry, plant operators, and the scientific community with information covering the results of the performance analysis.
Date: September 15, 1964
Creator: Darley, D. K.
System: The UNT Digital Library
Sodium Graphite Reactor, Quarterly Progress Report, March-June 1954 (open access)

Sodium Graphite Reactor, Quarterly Progress Report, March-June 1954

"The Atomic energy Commission has undertaken a development program to provide the technology needed for the evaluation and economic design of nuclear power plants. This program is to be carried out during the next five years at several national laboratories and industrial organizations. The Sodium Graphite Reactor (the SGR) is one of those to be investigated and experimentally tested as part of this 5-year effort. The program on the SGR is intended to expand our area of information covering sodium-graphite technology, experimentally demonstrate the feasibility of this reactor complex and extend its performance limits, and apply in information developed to designs suitable for the full-scale nuclear power plant. As a principal part of this program, a Sodium Reactor Experiment (the SRE) is to be constructed and operated; it will be the major experimental facility in which the performance of this reactor will be studied and new technological advances tested. This report continues an earlier series 2-7 in which previous work on the SGR and the SRE has been described. In this report, the progress on the program is described in two main sections. Section A is devoted to work relating to the general technology of Sodium Graphite Reactors, and to …
Date: September 1, 1954
Creator: Siegel, Sidney & Inman, Guy M.
System: The UNT Digital Library