Joint Research Centre fusion materials irradiations in HFR : present status and prospectivesFunded under: FP1-FUSION 9C
The materials under investigation in the frame of the Fusion Technology and Safety Programme are: Cr-Ni Austenitic steels (316-L type) and Cr-Mn Austenitic steels (AMCR and FI type) as structural materials and Pb-17Li eutectic as tritium breeding material. The experiments on structural materials comprise sample irradiations with post-irradiation tensile tests (FRUST), sample irradiations under constant load and post-irradiation strain measurement (TRIESTE) and on-line creep tests (CRISP). The experiments on Pb-17Li breeder materials consist of sample irradiations to investigate tritium production and recovery, as well as tritium permeation through blanket structures (LIBRETTO Experiment). Future developments of the testing programmes at HFR Petten are discussed. These may include materials for divertor applications and advanced low activation composite materials for commercial power reactors.
Bibliographic Reference: EUR 12329 EN (1989) MF, 27 pp., ECU 4, blow-up copy ECU 5
Record Number: 198911124 / Last updated on: 1994-12-01
Original language: en
Available languages: en