Published December 1993 | Version v1
Report

Computer simulation of tritium retention and release in irradiated beryllium

  • 1. Kernforschungszentrum Karlsruhe, Inst. fuer Neutronenphysik und Reaktortechnik (Germany)
  • 2. European Synchrotron Radiation Facility, 38 Grenoble (France)
  • 3. Commission of the European Communities, Joint Research Centre, Karlsruhe Establishment, European Inst. for Transuranium Elements (Germany)

Description

The helium produced by the 9Be(n,2n)2 4He 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 oxyde and capture in helium bubbles. The resulting modified code allows the calculation of tritium distribution and release from beryllium. Good agreement between calculated and experimental data was found. (orig.)

Part of:
Workshop on beryllium for fusion applications. Proceedings. IEA Implementing Agreement for a Programme of Research and Development on Fusion Materials

Additional details

Publishing Information

Imprint Title
Workshop on beryllium for fusion applications. Proceedings. IEA Implementing Agreement for a Programme of Research and Development on Fusion Materials
Imprint Pagination
349 p.
Journal Page Range
p. 149-163.
ISSN
0303-4003
Report number
KFK--5271

Conference

Title
Workshop on beryllium for fusion applications.
Dates
4-5 Oct 1993.
Place
Karlsruhe (Germany).

Optional Information