MODELING OF SWELLING AND TRITIUM RELEASE IN IRRADIATED BERYLLIUM

Citation
M. Dalledonne et al., MODELING OF SWELLING AND TRITIUM RELEASE IN IRRADIATED BERYLLIUM, Journal of nuclear materials, 215, 1994, pp. 954-960
Citations number
22
Categorie Soggetti
Nuclear Sciences & Tecnology","Metallurgy & Mining","Material Science
ISSN journal
00223115
Volume
215
Year of publication
1994
Part
B
Pages
954 - 960
Database
ISI
SICI code
0022-3115(1994)215:<954:MOSATR>2.0.ZU;2-9
Abstract
The most important effects of neutron irradiation on beryllium are swe lling, embrittlement and tritium retention. The helium produced by the Be-9(n, 2n)2(4)He reaction is the cause of beryllium swelling and, at high neutron fluences, the main cause of tritium retention which is p roduced by simultaneous reactions. It was, therefore, decided to devel op a computer code capable of describing the helium and tritium behavi our in beryllium. The approach used was to modify an existing code ava ilable for the modelling of fission gas behaviour in UO2 irradiated in fission reactors. A new model describing the trapping effects on trit ium due to chemical reactions and capture in helium-bubbles has been i ncluded in the code. The resulting code ANFIBE (ANalysis of Fusion Irr adiated BEryllium) allows the calculation of gas distribution, induced swelling and helium and tritium release from beryllium. Good agreemen t between experimental and calculated swelling and tritium release has been found.