Tritium distribution in JT-60U W-shaped divertor

Hydrogen isotopes retention in the outboard first wall tiles of JT-60U

“…JT-60U was a high ripple loss machine and high energy particles could easily escape to the first wall by the ripple loss mechanism. According to the orbit following Monte Carlo (OFMC) simulation [15], the ripple loss is high at the mid-plane and divertor dome area [9,10]. This is consistent with high D/H observed in the 15Ga1 and 15Ek1 tiles which are located near the mid-plane.…”

Tritium uptake in graphite tiles exposed to EAST plasma and then tritium gas

“…The IP can detect tritium distributed within the depth of about 3.5 m from the surface of the carbon-based tile [9]. Before the IP measurement, one piece of each kind of the sample exposed in 400 • C was cut into small pieces of 15 mm × 2 mm × 3 mm by a micro cutter (MC-201N, MARUTO) with a linear velocity of 0.375 m/s.…”

Overview of research and development activities on fusion nuclear technologies in Japan

“…In JT-60U, quite recently, PMI and PFM studies have started under the joint research between Japanese Universities and JAERI [28,29]. The studies were focused on those relating tritium issues of ITER, in particular, retention of hydrogen isotopes (H, D, T) in plasma facing carbon materials and erosion/deposition including dust formation.…”

“…The studies were focused on those relating tritium issues of ITER, in particular, retention of hydrogen isotopes (H, D, T) in plasma facing carbon materials and erosion/deposition including dust formation. T retention profile in the divertor area was completely separated from H and D profiles because most of T produced by DD reaction was implanted directly into the plasma facing surface without fully loosing its initial energy [28,29]. On the other hand, H and D retention profiles in the divertor region well correlated with the carbon deposition profiles [30].…”