Materials Engineering Associates, Lanham, MD
Pages: 14 Published: Jan 1989
This report describes a set of experiments undertaken using a 2 MW test reactor, the UBR, to qualify the significance of fluence rate to the embrittlement produced in reactor pressure vessel steels at their service temperature. Test materials include two reference plates (A 302-B, A 533-B steel) and two submerged arc weld deposits (Linde 80, Linde 0091 welding fluxes). Specimen types are Charpy-V (Cc), tension, and 0.5T compact tension specimens. Target fluence rates are 8 × 1010, 6 × 1011 and 9 × 1012 n/cm2 s-1. Initial findings are reported. The data describe a fluence rate effect which may extend to power reactor surveillance as well as test reactor facilities now in use. A different embrittlement sensitivity versus fluence rate relationship was observed for the A 302-B plate compared with the Linde 80 weld deposit.
A 302-B steel, A 533-B steel, submerged arc welds, radiation effects, radiation embrittlement sensitivity, neutron fluence rate, dose-rate effects, notch ductility, Charpy-V test, tension test, neutron irradiation, nuclear reactors
Paper ID: STP10114S