Development of radiation resistant grades of beryllium for nuclear and fusion facilities

Conference · Fri Sep 01 04:00:00 EDT 1995

OSTI ID:212920

Kupriyanov, I B; Gorokhov, V A; Nikolaev, G N ^[1]

---

1. Russia Research Institute of Inorganic Materials, Moscow (Russian Federation)

R&D results on beryllium with high radiation resistance obtained recently are described in this report. The data are presented on nine different grades of isotropic beryllium manufactured by VNIINM and distinguished by both initial powder characteristics and properties of billets, made of these powders. The average grain size of the investigated beryllium grades varied from 8 to 26 {mu}m, the content of beryllium oxide was 0.9 - 3.9 wt.%, the dispersity of beryllium oxide - 0.04 - 0.5 {mu}m, tensile strength -- 250 - 650 MPa. All materials were irradiated in SM - 2 reactor over the temperature range 550 - 780{degrees}C. The results of the investigation showed, that HIP beryllium grades are less susceptible to swelling at higher temperatures in comparison with hot pressed and extruded grades. Beryllium samples, having the smallest grain size, demonstrated minimal swelling, which was less than 0.8 % at 750{degrees}C and Fs = 3.7 {center_dot}10{sup 21} cm{sup -2} (E>0.1 MeV). The mechanical properties, creep and microstructure parameters, measured before and after irradiation, are presented.

• Research Organization: Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
• OSTI ID: 212920
• Report Number(s): CONF-9509218--; ON: DE96002404
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BERYLLIUM BASE ALLOYS
DAMAGING NEUTRON FLUENCE
DESIGN
ITER TOKAMAK
PHYSICAL RADIATION EFFECTS
RADIATION HARDENING
SWELLING
TENSILE PROPERTIES
THERMONUCLEAR REACTOR MATERIALS