Hinkle, Norman E.
Oak Ridge National Laboratory, Oak Ridge, Tenn.
Pages: 19 Published: Jan 1963
Stress-rupture experiments are being operated in the Oak Ridge Research Reactor to study the effect of neutron bombardment on the rupture strength and deformation characteristics of stressed tubular specimens at controlled elevated temperatures in oxidizing or inert gas environments. The materials being investigated are Inconel alloy 600, type 304 stainless steel, Zircaloy-2, and a columbium - 1 per cent zirconium alloy. The rupture strength of Inconel alloy 600 at 1500 F is decreased as much as 25 per cent during irradiation. Smaller losses of rupture strength are observed for type 304 stainless steel at 1300 to 1500 F and the columbium alloy at 1800 F. No major change is observed for Zircaloy-2 at 700 or 900 F. The deformation-at-rupture of the Inconel and stainless steel alloys is generally lowered and metallographic evidence indicates that these premature ruptures occur because of lowered grain boundary cohesion.
Paper ID: STP41760S