Dv. Andreev et al., POSTIRRADIATION STUDIES OF BERYLLIUM REFLECTOR OF FISSION REACTOR - EXAMINATION OF GAS-RELEASE, SWELLING AND STRUCTURE OF BERYLLIUM UNDER ANNEALING, Journal of nuclear materials, 237, 1996, pp. 880-885
Citations number
6
Categorie Soggetti
Nuclear Sciences & Tecnology","Mining & Mineral Processing","Material Science
Hot-pressed high-density (TShG-type) beryllium was irradiated at 100 d
egrees C up to the fast neutron fluence of 1 x 10(26) n/m(2). Transmut
ation tritium and helium contents were 652 and 4400 appm, respectively
. Post-irradiation studies of beryllium consist of optical and electro
n microscopy, density measurements before and after isochronal anneali
ng at the temperature range of 300-1100 degrees C and thermodesorption
gas spectrometry. Investigation shows the following: (1) Slight swell
ing of beryllium after neutron irradiation. (2) Spatial non-uniformity
in the distribution of the pores. (3) Complicated dependence of swell
ing on annealing temperature caused by formation of gas porosity. In t
he temperature range from 500 to 800 degrees C, swelling of beryllium
was probably caused by growth of bubbles because of tritium mobility.
At the temperature above 900 degrees C swelling of beryllium was proba
bly caused by growth of bubbles because of helium mobility. (4) Full d
egassing of the irradiated beryllium took place below its melting temp
erature.