High heat flux heater development status report (open access)

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 (open access)

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 (open access)

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