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The helium produced by the 9Be(n,2n)2(4)He reaction and the oxygen impurities present in the material appear to be the main cause of tritium retention in irradiated beryllium. Because of the strong relation between the helium bubbles distribution and tritium release, it was decided to extend the code ANFIBE (ANalysis of Fusion Irradiated BEryllium), initially used to describe the helium induced swelling in beryllium, by including a new model describing the trapping effects on tritium due to chemical reactions with beryllium oxide and capture in helium bubbles. The resulting modified code allows tritium distribution and release from beryllium to be calculated. Good agreement between calculated and experimental data is found. However, more tritium retention/release data are needed for ANFIBE validation.

Additional information

Authors: DALLE DONNE M, Kernforschungszentrum Karlsruhe, Institut für Neutronenphysik und Reaktortechnik (DE);SCAFFIDI-ARGENTINA F, Kernforschungszentrum Karlsruhe, Institut für Neutronenphysik und Reaktortechnik (DE);FERRERO C, European Synchrotron Radiation Facility, Grenoble (FR);RONCHI C, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: International Workshop on Fusion Materials, Karlsruhe (DE), October 4-6, 1993
Availability: Available from (1) as Paper EN 37986 ORA
Record Number: 199311600 / Last updated on: 1994-11-28
Original language: en
Available languages: en