An Engineering Test Program to Investigate a Loss of Coolant Accident (open access)

An Engineering Test Program to Investigate a Loss of Coolant Accident

From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."
Date: October 1964
Creator: Wilson, T. R.; Hauge, O. M.; Matheney, G. B. & Homer, G. B.
System: The UNT Digital Library
EOCR Control Rod and Driver Fuel Hydraulic Tests (open access)

EOCR Control Rod and Driver Fuel Hydraulic Tests

Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date: October 19, 1962
Creator: Harrison, L. J.
System: The UNT Digital Library
Final Summary Report of the Gas-Cooled Reactor Experiment-1 (open access)

Final Summary Report of the Gas-Cooled Reactor Experiment-1

Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
Date: October 1963
Creator: Chesworth, R. H.
System: The UNT Digital Library
Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation (open access)

Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation

Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
Date: October 1963
Creator: Phillips Petroleum Company
System: The UNT Digital Library
Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide (open access)

Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide

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).
Date: October 3, 1958
Creator: Jones, L. H.
System: The UNT Digital Library
Zirconium Processing Capability of the Idaho Chemical Processing Plant (open access)

Zirconium Processing Capability of the Idaho Chemical Processing Plant

Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.
Date: October 1964
Creator: Bower, J. R.
System: The UNT Digital Library