Retention and features of deuterium detrapping from radiation-induced damages in steels

• Дата: 2009
• Автори: Tolstolutskaya, G.D., Ruzhytskiy, V.V., Karpov, S.A., Kopanets, I.E.
• Формат: Стаття
• Мова: English
• Опубліковано: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2009
• Назва видання: Вопросы атомной науки и техники
• Онлайн доступ: http://dspace.nbuv.gov.ua/handle/123456789/96345
• Назва журналу: Digital Library of Periodicals of National Academy of Sciences of Ukraine
• Цитувати: Retention and features of deuterium detrapping from radiation-induced damages in steels / G.D. Tolstolutskaya, V.V. Ruzhytskiy, S.A. Karpov, I.E. Kopanets // Вопросы атомной науки и техники. — 2009. — № 4. — С. 29-41. — Бібліогр.: 21 назв. — англ.

The accelerators and ion-beam analysis techniques are used for simulation of displacement damage and detailed investigation of distribution profiles of damage and impurity gas atoms (especially helium and hydrogen) in the irradiation of targets for a wide ranges of doses and particle energies. The influence of preimplanted helium and heavy ion-induced damage on deuterium trapping in austenitic and ferritic/martensitic steels was studied. The results obtained for 18Cr10NiTi stainless steel show that ion-implanted deuterium is weakly trapped by defects produced in 5 keV D+ displacement cascades. The effective trapping temperature interval is between 300 and 600 К. The characteristics of trapping and the temperature range of hydrogen isotopes retention in traps formed by prior implantation of helium depend on the concentration of implanted helium and on the type of defects developed. The formation of helium bubbles in 18Cr10NiTi steel causes an order of magnitude increase in the content of retained deuterium atoms in the range of temperature 300-600 K and extends the interval of effective trapping temperatures to 1000 K. Energetic heavy-ion irradiation (1.4 MeV Ar+ ) has been used for modeling defect cluster formation under displacement cascade conditions to simulate fusion reactor environments. It was found that retention of hydrogen and deuterium strongly increased in this case. It is shown that the presence of a surface-passive film considerably shifts the gas release interval to higher temperatures and reduces the deuterium surface recombination coefficient by several orders of magnitude.