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Hydrogen and deuterium in graphite limiters from TFTR, PDX and PLT

Conference ·
OSTI ID:5791351
Retention of hydrogen isotopes in graphite limiters impacts plasma fueling, isotope changeover rates and tritium inventory in fusion reactors. This paper describes measurements of the amount of euterium (D) in graphite tiles from the TFTR limiter, and in graphite limiters from PDX and PLT, after extended exposure to high power D plasmas. D concentrations decreased abruptly over the first micron and fell to the bulk value of 4 to 13 atomic, ppM beyond 40 microns from the exposed surface. The average near-surface aeral densities of D on the TFTR tiles was 10/sup 17/ D/cm/sup 2/. The total amount of near-surface D in TFTR limiters estimated using this value is larger than the amount of D in a plasma but small compared to the allowed tritium inventory. The D concentrations found in the bulk are large enough to be an important factor for tritium inventory. The 1 at. % of hydrogen (H) found in the limiters and in graphite not exposed to plasma may be an important source of hydrogen to the plasma. We discuss the influence of the H and D concentrations found in the bulk of graphite on tritium inventory estimates and hydrogen isotope changeover rates.
Research Organization:
Sandia National Labs., Albuquerque, NM (USA); Sandia National Labs., Livermore, CA (USA)
DOE Contract Number:
AC04-76DP00789
OSTI ID:
5791351
Report Number(s):
SAND-85-2735C; CONF-860522-7; ON: DE86011419
Country of Publication:
United States
Language:
English