ANFIBE: A comprehensive model for swelling and titrium release from neutron irradiated beryllium
A new computer code called analysis of fusion irradiated beryllium (ANFIBE) has been developed to describe the most important processes (diffusion, gas precipitation, bubble coalescence, helium-bubble trapping, chemical trapping, etc) which are thought to affect gas behaviour and swelling in beryllium during fast neutron irradiation. The new model allows the prediction of helium and tritium re-distribution, induced swelling, and release. The relevant effects occurring in irradiated beryllium under steady or transient temperature conditions have been considered from a microscopic (lattice and subgranular volume elements), structural (metallographic features of the material) and geometrical (specimen design parameters) point of view. This paper, which represents the second part of the presentation of this model, contains the main results of the validation work. The relevant beryllium properties published in the literature are presented and critically examined. The performance of the code was assessed by comparing the code predictions with a large set of published experimental data on swelling and gas release in beryllium under fast neutron irradiation.
Bibliographic Reference: Article: Nuclear Technology (1997)
Record Number: 199810122 / Last updated on: 1998-02-12
Original language: en
Available languages: en