Published September 1992 | Version v1
Journal article

Microscopic tritium behavior in ion-irradiated austenitic steels

  • 1. Nuclear Engineering Lab., Toshiba Corp., Yokohama (Japan)
  • 2. Dept. of Materials Sciences and Engineering, Univ. of Tokyo (Japan)
  • 3. Nuclear Engineering Research Lab., Univ. of Tokyo (Japan)
  • 4. Inst. of Industrial Science, Univ. of Tokyo (Japan)

Description

Fe-Cr-Ni ternary alloys were irradiated with 3 MeV nickel ions and charged with tritium, after which they were investigated by transmission electron microscopical autoradiography (TEM-ARG) to confirm compatibility between the alloy and tritium. The results suggest that tritium is trapped in radiation-induced lattice defects, such as vacancies and dislocation, as well as especially at radiation-induced voids and at grain boundaries at about 10 to 100 dpa radiation damaged levels. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
191-194
Journal Issue
pt.B
Journal Page Range
p. 759-765.
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
5. international conference on fusion reactor materials (ICFRM-5).
Dates
17-22 Nov 1991.
Place
Clearwater, FL (United States).