Materials Engineering, Lanham, MD
Pages: 26 Published: Jan 1994
The influence of irradiation temperature on the extent of change in Charpy-V (Cv) notch ductility and tension test properties of low alloy structural steels and welds was explored for reactor vessel applications. Specimens were irradiated at 288°C and 316°C in temperature-controlled assemblies in the Ford Nuclear Reactor (FNR) at the University of Michigan. Irradiation at 316°C to 7.9 × 1018 n/cm2, E > 1 MeV, produced 41-J temperature elevations that were on average 51% of those produced by 260°C irradiation. Thermal aging at 316°C for 5000 h had little effect on Cv and tension test properties. NRC Regulatory Guide 1.99 Rev. 2 projections for irradiation-induced embrittlement at 288°C are compared to the experiment measurements.
pressure vessel steels, nuclear reactors, low alloy steels, submerged arc welds, radiation embrittlement, notch ductility, tensile properties, radiation sensitivity, neutron irradiation, Regulatory Guide 1.99
Paper ID: STP23944S