ANFIBE: A Comprehensive Model for Swelling and Tritium Release from Neutron-Irradiated Beryllium—II: Comparison of Model Predictions with Experimental Results

Abstract

A new computer code, called ANFIBE (ANalysis of Fusion Irradiated BEryllium), has been developed to describe the most important processes (diffusion, gas precipitation, bubble coalescence, helium-bubble trapping, chemical trapping, etc.) thought to affect gas behavior and swelling in beryllium during fast neutron irradiation. The new model allows the prediction of helium and tritium redistribution, 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.The main results of this validation work represent the second part of the presentation of this model. The relevant beryllium properties published in the literature are presented and critically examined. The performance of the code is 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.