Tritium retention in neutron-irradiated low-Z materials for use as plasma facing materials

Journal of Nuclear Materials

Volumn 290-293, Issue , 2001, Pages 211-215

  Scaffidi Argentina, F ^a   Sand, C ^a   Wu, C H ^b  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^b MAX PLANCK INSTITUT FÜR PLASMAPHYSIK   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

BERYLLIUM; GRAPHITE; NEUTRON IRRADIATION; PLASMAS; TRITIUM;

PLASMA FACING MATERIALS;

FUSION REACTORS;

EID: 0035276245     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(00)00565-1     Document Type: Article

References (9)

1. P. Franzen et al., Nucl. Fus. 37 (10) (1997) 1374.
2. J.P. Bonal, D. Moulinier, Thermal properties of advanced carbon fiber composites for fusion application, Report DMT/95-495, SEMI/LEMA/95-073, Commisariat À l'Energie Atomique, Direction des Réacteurs Nucléaires, Saclay, October 1995.
3. R. Conrad, PARIDE: Irradiation of plasma facing materials for demo at the high flux reactor petten. Projects D 302.1 and D 302.2, Technical Memorandum HFR/4439, Joint Research Center, Institute of Advanced Materials, Petten, October 1997.
4. H. Kwast et al., Phys. Scr. T64 (1996) 41.
5. L. Sannen, Final report characterisation of irradiated beryllium, SCK-CEN Report FT/Mol/92-01, Mol, July 1992.
6. R.A. Anderl et al., Fus. Technol. 28 (1995) 1114.
7. R.A. Anderl et al., in: Proceedings of the Third IEA International Workshop on Beryllium Technology for Fusion, Mito City, Japan, 22-24 October 1997.
8. F. Scaffidi-Argentina, H. Werle, in: Proceedings of the Second IEA International Workshop on Beryllium Technology for Fusion, Jackson Lake Lodge, Wy, 6-8 September 1995.
9. F. Scaffidi-Argentina et al., in: Proceedings of the Fifth International Symposium on Fusion Nuclear Technology, Rome, Italy, 19-24 September 1999, to be published.