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Comparison of Two Sodium-Cooled, 1000 MegaWatt Fast Reactor Concepts: Task 1 Report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work
From introduction: "The development of one or more nuclear steam supply system concepts, with certain trade-off studies to aid in the definition of these concepts. The selection of a reference concept for further study."
Date:
June 1968
Creator:
General Electric Company
System:
The UNT Digital Library
High heat flux heater development status report
The development of a high heat flux heater for use in corrosion rate and stress-rupture tests of fuel cladding materials in a sodium environment is described.
Date:
June 15, 1968
Creator:
McKisson, R. L. & Babbe, E. L.
System:
The UNT Digital Library
Irradiation behavior of unalloyed hypostoichiometric uranium carbide, experiment AI 3-11 and review
A report regarding the irradiation behavior of Unalloyed hypostoichiometric uranium carbide experiment AI 3-11 and review
Date:
June 22, 1968
Creator:
Frank, J. E.; Forrester, R. E. & Buck, J. S.
System:
The UNT Digital Library
Irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12
A report regarding irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12
Date:
June 22, 1968
Creator:
Arnold, J. L.
System:
The UNT Digital Library