Author/Authors :
Leichtle، نويسنده , , D. and Arbeiter، نويسنده , , F. and Dolensky، نويسنده , , B. and Fischer، نويسنده , , U. and Gordeev، نويسنده , , S. and Heinzel، نويسنده , , V. and Ihli، نويسنده , , T. and Lang، نويسنده , , K.-H. and Moeslang، نويسنده , , A. and Simakov، نويسنده , , S.P. and Slobodchuk، نويسنده , , V. and Stratmanns، نويسنده , , E.، نويسنده ,
Abstract :
The International Fusion Material Irradiation Facility (IFMIF) is an accelerator driven neutron source for irradiation tests of candidate fusion reactor materials. Within the High Flux Test Module (HFTM) a testing volume of 0.5 l filled by qualified small scale specimens will be irradiated at displacement rates of 20–50 dpa/fpy in structural materials. The Forschungszentrum Karlsruhe (FZK) has developed a HFTM design which closely follows the design premise of maximising the space available for irradiation specimens in the IFMIF high flux zone and in addition allows keeping the temperature nearly constant in the rigs containing the specimen. Complementary analyses on nuclear, thermo-hydraulics and mechanical performance of the HFTM were performed to optimize the design. The present paper highlights the main design characteristics as well as recent progress achieved in this area.
ntribution also includes (i) recommendations for the use of container, rig and capsule materials, and (ii) a description of the fabrication routes for the entire HFTM including brazing and filling procedures which are currently under development at the Forschungszentrum Karlsruhe.