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Survey of Materials for Supercritical-Water Reactor
Survey of properties of materials which might be suitable for use in various locations in a supercritical-water reactor. Properties examined include tensile strength, rupture strength, endurance strength, Young's modulus, tensile elongation, coefficient of thermal expansion, coefficient of thermal conductivity, density, nominal composition, usual heat treatments and thermal-neutron-absorption cross sections.
Date:
November 27, 1953
Creator:
Udy, Murray C. & Boulger, Francis W.
System:
The UNT Digital Library