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Application of Fast Neutron Removal Theory to the Calculation of Thermal Neutron Flux Distributions in Reactor Shields
Abstract: A calculational method is presented which may be used to determine fast and thermal neutron flux distributions at deep neutron penetrations in hydrogenous shields.
Date:
1958
Creator:
Duncan, David S. & Whittum, H. O., Jr.
System:
The UNT Digital Library
Remote Maintenance Techniques for the Processing Refabrication Experiment
Abstract: This report outlines the general techniques developed for replacement of PRE in-cell equipment or equipment components.
Date:
December 1, 1958
Creator:
Stoker, Donald J.
System:
The UNT Digital Library
Organic Moderated Reactor Experiment : Safeguards Summary
Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date:
February 1, 1958
Creator:
Sletten, H. L. & Blue, L. R.
System:
The UNT Digital Library
Organic Reactor Waste Gas Analyzer
The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).
Date:
October 15, 1958
Creator:
Gilroy, H. M. & Edwards, R. J.
System:
The UNT Digital Library