Deuterium retention in ITER-grade austenitic stainless steel

摘要: In view of the construction ITER, it is essential to confirm that retention tritium by large interior surface area stainless steel will not become an issue for safety or operating inventory reasons. Retention deuterium in ITER-grade austenitic samples was studied during t = 24 h exposures pure gaseous at p 0.01 mbar and 0.1 T 100 °C, 250 °C 400 respectively. The required high sensitivity distinguishing hydrogen isotopes involved process (H2, HD D2) gained after suppression native concentration a thermal treatment 200 h. quantity retained determined measuring absolute pressure change exposure subsequent mass spectrometry revealing intense isotope exchange reaction. amount 2.6 × 1016 D cm−2 highest noticeably less lower temperature. Our results, when compared with similar exposures, do exceed limits set generic analysis ITER. They manifest extremely absorption release can be precise technique, otherwise attributed exclusively scintillation methods.