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Nuclear Technology, Volume 11, No. 1 (May 1971)
Influence of Irradiation Temperature on the Creep-Rupture Properties of Hastelloy-N

Welding Journal, Volume 50, No. 2 (February 1971)

Nuclear Applications and Technology, Volume 8, No. 2 (February 1970)
Molten-Salt Reactors-History, Status, and Potential
Experience with the Molten-Salt Reactor Experiment
Molten-Salt Reactor Chemistry
New Developments in Materials for Molten-Salt Reactors
Engineering Development of the MSBR Fuel Recycle
Graphite and Xenon Behavior and their Influence on Molten-Salt Reactor Design
The Design and Performance Features of a Single-Fluid Molten-Salt Breeder Reactor
Reactor Physics and Fuel-Cycle Analyses

Journal of Nuclear Materials, Volume 31, No. 3 (July 1969)
Diffusion of Titanium in Modified Hastelloy N

Journal of Nuclear Materials, Volume 31, No. 1 (May 1969)
Variation of the Mechanical Properties of Irradiated Hastelloy N with Strain Rate

Nuclear Engineering and Design, Volume 9, No. 2 (February 1969)
Graphite Behavior and its Effects on MSBR Performance

Nuclear Applications, Volume 4, No. 2 (February 1968)
Stress-Rupture Properties of Irradiated and Unirradiated Hastelloy N Tubes

Nuclear Applications, Volume 2, No. 6 (December 1966)
Creep-Rupture Properties Under Conditions of Constant and Varying Stresses