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UC Fuel Element Design and Fabrication
Abstract: Uranium monocarbide shows considerable potential for use as a fuel in high temperature, high power density, nuclear power reactors. As Atomics International is proposing its use in sodium graphite type reactors, it was necessary to develop a process for fabricaing sodium bonded uranium carbide fuel elements.
Date:
August 1, 1964
Creator:
Draganchuk, W.
System:
The UNT Digital Library
Boiling Depressurization Transients
Abstract: An analytical and experimental effort toward a better understanding of the mechanisms involved in nuclear power reactor loss-of-pressure accidents is presented.
Date:
August 1, 1964
Creator:
Halfen, F. J. & Berganzoli, F.
System:
The UNT Digital Library
Uranium Carbide Transient Heating Experiments - Phase 1
Abstract: Two in-pile capsules containing mock-up uranium carbide fuel rods were subjected to a total of five neutron bursts in the TREAT facility with initial reactor periods ranging from 0.26 to 0.10 sec.
Date:
August 1, 1964
Creator:
Stachura, S. J.; Silberberg, M. & Cordy, R. N.
System:
The UNT Digital Library
The Continuous Neutron Flux Monitor Project: An Interim Report
Abstract: A new concept for continuously monitoring neutron flux has been successfully tested.
Date:
August 1, 1964
Creator:
Smith, Charles R. F. & Springer, Thomas H.
System:
The UNT Digital Library