Low-temperature low-dose neutron irradiation effects on beryllium

摘要: Abstract Mechanical property results are presented for high quality beryllium materials subjected to low-temperature, low-dose neutron irradiation in water-moderated reactors. Materials chosen were the S-65C ITER candidate material produced by Brush Wellman, Kawecki Berylco Industries P0 beryllium, and a high-purity zone refined beryllium. Mini-sheet tensile thermal diffusivity specimens irradiated temperature range of ∼100–300 °C with fast ( E >0.1 MeV) fluence 0.05–1.0 × 10 25 n/m 2 flux isotope reactor (HFIR) at Oak Ridge National Laboratory beam (HFBR) Brookhaven Laboratory. As expected from earlier work on both underwent significant embrittlement corresponding reduction ductility increased strength. Both volumetric expansion measured found have negligible changes this range. Of significance is that while rapidly embrittle these relevant conditions, some (1–2%) remains, which contrasts body including recent Brush-Wellman slightly higher fluence.