2007
DOI: 10.1016/j.jnucmat.2007.01.112
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Deuterium depth profiling in JT-60U tiles using the D(3He,p)4He resonant nuclear reaction

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Cited by 15 publications
(7 citation statements)
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“…For most devices, the long term retention fraction coming from integrated particle balance (F long $ 10-20%) is larger than what is deduced from post mortem analysis of PFCs [45]. However, both these methods are subject to large error bars 2 : it is difficult to accurately estimate the recovery over long time periods for particle balance on the one hand [46,47], while post mortem analysis is often based on a restricted set of samples, and assumes toroidal/poloidal symmetry to reconstruct the global inventory on the other hand [48][49][50][51]. Extrapolation to ITER with F long = 10%, assuming a gas puff rate of 100 Pam 3 s À1 for 50-50% of D-T, yields an equivalent long term retention of 5 g of T per 400 s shot (which means in reality a higher value after the shot), therefore limiting the number of shots to 70 before reaching the safety limit of 350 g.…”
Section: Disruptionmentioning
confidence: 99%
“…For most devices, the long term retention fraction coming from integrated particle balance (F long $ 10-20%) is larger than what is deduced from post mortem analysis of PFCs [45]. However, both these methods are subject to large error bars 2 : it is difficult to accurately estimate the recovery over long time periods for particle balance on the one hand [46,47], while post mortem analysis is often based on a restricted set of samples, and assumes toroidal/poloidal symmetry to reconstruct the global inventory on the other hand [48][49][50][51]. Extrapolation to ITER with F long = 10%, assuming a gas puff rate of 100 Pam 3 s À1 for 50-50% of D-T, yields an equivalent long term retention of 5 g of T per 400 s shot (which means in reality a higher value after the shot), therefore limiting the number of shots to 70 before reaching the safety limit of 350 g.…”
Section: Disruptionmentioning
confidence: 99%
“…In this situation, the fuel retention is mainly ascribed to the following two processes: (1) the permeation of hydrogen deep into the wall and (2) the co-deposition of hydrogen with impurities such as carbon. The retention rate due to permeation reduces with the ion fluence [1,2], and the fuel retention by the co-deposition works in both short-and long-pulse discharges. Hence, by the decrease in the surface absorption rate and the permeation rate, the controllability of the plasma density is assumed to be lower in a long-pulse discharge than in a short-pulse discharge.…”
Section: Introductionmentioning
confidence: 99%
“…Because of its high thermal shock resistivity and high thermal conductivity, carbon material is a candidate as a divertor target in ITER. Carbon materials are easily eroded by incident hydrogen bombardment and the sputtered carbon atoms are co-deposited with hydrogen isotopes on the walls nearby the divertor target [2][3][4][5][6]. Hydrogen isotopes retention in carbon films retained by co-deposition and implantation processes have been well investigated so far [7,8].…”
Section: Introductionmentioning
confidence: 99%