29th Symposium on Fusion Technology (SOFT 2016)

P3.161 Post irradiation examination of High Dose irradiated Beryllium (HIDOBE-02) in the High Flux Reactor

7 Sep 2016, 11:00

1h 20m

Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Board: 161

Poster H. Fuel Cycle and Breeding Blankets P3 Poster session

Speaker

Lida Magielsen (Research and Innovation)

Description

In the frame of the European Tritium Breeder blanket development for DEMO, two high dose irradiations of beryllium and beryllides, to be used as neutron multiplier, have been performedin the High Flux Reactor Petten (NL). From one irradiation, to 3000 appm He, the post irradiation results have been published in previous proceedings. In the second High Dose Beryllium irradiation (HIDOBE-02), various grades of beryllium pebbles, pellets and Titanium Beryllide samples have been neutron irradiated in the temperature range of 425- 850 ^ooC until the 30% End of Life (EOL) DEMO relevant Helium content of around 6000 appm He was achieved. The Post-Irradiation Examination (PIE) of HIDOBE samples has the objective to collect and analyse information about changes in the Be materials properties after irradiation. Measurements include dimensional changes, microstructure,  thermal properties and tritium release. These results are compared with as received material and Beryllium irradiated to 3000 appm He.   This paper will focus on the microstructure of the unconstrained and contrained pebbles and beryllide grades. It will be shown that after irradiation the material shows open porosity, which is dependent on irradiation temperature. Also the correlation of the irradiation temperature, porosity and results from tritium release desorption experiments will be investigated.