Effects of neutron irradiation at 70–200 °C in beryllium

摘要: Abstract At present beryllium is considered one of the metals to be used as a plasma facing and blanket material. This paper presents investigations several Russian grades fabricated by HE HIP technologies. Beryllium specimens were irradiated in SM reactor at 70–200 °C up neutron fluence (0.6–3.9)×1022 cm−2 (E>0.1 MeV). It shown that relative mass decrease contact with water coolant during irradiation achieved value >1.5% maximum dose. Swelling was range 0.2–1.5% monotonically increasing During mechanical tensile compression tests could observe absolute brittle destruction reduced strength level comparison initial state. A comparatively higher observed on 200 °C. The basic type intergranular some fraction transgranular chip.