Irradiation of lithium zirconate pebble-bed in BEATRIX-II Phase II

Ceramic breeder materials: Status and needs

“…Material " fracture was not observed in the ceramic breeder material. Lifetime tritium release of Li2Zr03 pebbles showed very low tritium inventory and excellent performance of pebbles to 11 OO°C for -200 FPD [36].…”

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li2TiO3Pebble Bed in Japan

“…However, the tritium recovery rate of 1,000 ppmH 2 became the same as the value at 10,000 ppmH 2 after about 5 h from changing the hydrogen content. In the BEATRIX-II, [7][8][9] increasing the hydrogen content in sweep gas resulted in a transient tritium recovery peak which indicated a decrease in tritium inventory in the specimen. Decreasing hydrogen concentration from the reference sweep gas (1,000 ppmH 2 ) resulted in an increase in the tritium inventory.…”

“…The major advantage of in-situ irradiation experiments is the capability to provide a neutron flux over a large volume prior to the availability of a fusion reactor. As the recent insitu irradiation tests, CRITIC-III (Canada), 6) BEATRIX-II (US/Japan/Canada), [7][8][9] EXOTIC (Netherlands/EU) [10][11][12] and others were conducted. However, these experiments used relatively small amount of specimen for characterization of tritium breeders and the structures of a fusion blanket have not been simulated.…”

In situ tritium recovery behavior from Li2TiO3 pebble bed under neutron pulse operation

“…The major advantage of in situ irradiation experiments is its capability to provide such information with respect to neutron flux over a large volume prior to availability of a fusion reactor. Up to now, in situ irradiation tests such as CRITIC-III (Canada) [1], BEATRIX-II (US/ Japan/Canada) [2][3][4], EXOTIC (Netherlands/EU) [5][6][7] and others were conducted.…”