Out-of-pile tritium release study on Li4SiO4 pebbles from TRINPC-I experiments

D-depth profiling in as-implanted and annealed Li-based breeder blanket ceramics

“…Because of their properties (among others: high radiation resistance, low tritium retention and high tritium generation), Li-based ceramics are one of the most promising materials for breeder blankets [1]. In these materials the Tritium originates from the following nuclear reactions 6 Li (n, a) T or 7 Li (n, n a) T [2] taking place when the ceramics are irradiated with neutrons. The lost of T from neutron-irradiated lithium ceramics involves its diffusive motion within the solid and its subsequent release from the ceramic surface.…”

“…Moreover an additional factor, which has to be considered when studying T behaviour in irradiated materials, is the evolution of the microstructure during irradiation with energetic ions, neutrons and electrons [5]. A good number of in situ T release experiments testing several different irradiated materials have been carried out at different laboratories [6][7][8][9], the conclusions being that processes involved in the annihilation of radiation defects seem to play an important role to establish the T recovering system and the release behaviour.…”

Effect of water adsorption on tritium release from Li4SiO4

“…Two units of glycol bubblers are placed separately in the system for collecting tritiated water and tritium gas respectively as described in Ref. [2]. Li 4 SiO 4 specimens are heated with heating rate of 5°C/min from R.T. to 800°C and maintain at 800°C for about 1 h. Temperature of the sample is controlled with a conventional electric furnace and a thermocouple is placed outside the reactor tube without contacting directly with pebble samples.…”

“…Lithium orthosilicate (Li 4 SiO 4 ), as one of candidates of lithium ceramic breeder for fusion reactor, was researched previously by in-pile and out-of-pile tritium release experiments [1][2][3][4][5][6][7][8][9]. But the results of these experiments vary widely.…”