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Radiation Safety and Control Training Manual (open access)

Radiation Safety and Control Training Manual

Introduction: The Laboratory follows the recommendations of the National Committee on Radiation Protection concerning permissible exposure limits for those working with radiation. A system of controls and regulations has been established which should ensure that no person at the Laboratory will receive more than the permissible exposure. This manual is intended to provide the minimum background necessary for intelligent cooperation with the regulations.
Date: June 1, 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants (open access)

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Foreword: This report describes results of a series of evaluation and design studies conducted between July 1, 1960 and June 30, 1961, related to heavy water moderated power reactor plants.
Date: June 30, 1961
Creator: Chittenden, W. A. & Hoveke, G. F.
System: The UNT Digital Library
Engineering Test Reactor Critical Facility Control System Manual (open access)

Engineering Test Reactor Critical Facility Control System Manual

This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date: June 23, 1961
Creator: Meichle, F. A.
System: The UNT Digital Library
Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961 (open access)

Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: June 27, 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility (open access)

Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.
Date: June 1961
Creator: Muraoka, J.
System: The UNT Digital Library
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor (open access)

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date: June 1961
Creator: Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
System: The UNT Digital Library
Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy (open access)

Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.
Date: June 1961
Creator: Todd, R. H.
System: The UNT Digital Library