Tritium release from SS316 under vacuum condition

Journal Article · Sun Mar 15 04:00:00 EDT 2015 · Fusion Science and Technology

DOI:https://doi.org/10.13182/FST14-T93· OSTI ID:22429780

Torikai, Y.; Penzhorn, R. D. ^[1]

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1. Hydrogen Isotope Research Center, University of Toyama, Toyama (Japan)

The plasma facing surface of the ITER vacuum vessel, partly made of low carbon austenitic stainless steel type 316L, will incorporate tritium during machine operation. In this paper the kinetics of tritium release from stainless steel type 316 into vacuum and into a noble gas stream are compared and modelled. Type 316 stainless steel specimens loaded with tritium either by exposure to 1.2 kPa HT at 573 K or submersion into liquid HTO at 298 K showed characteristic thin surface layers trapping tritium in concentrations far higher than those determined in the bulk. The evolution of the tritium depth profile in the bulk during heating under vacuum was non-discernible from that of tritium liberated into a stream of argon. Only the relative amount of the two released tritium-species, i.e. HT or HTO, was different. Temperature-dependent depth profiles could be predicted with a one-dimensional diffusion model. Diffusion coefficients derived from fitting of the tritium release into an evacuated vessel or a stream of argon were found to be (1.4 ± 1.0)*10{sup -7} and (1.3 ± 0.9)*10{sup -9} cm{sup 2}/s at 573 and 423 K, respectively. Polished surfaces on type SS316 stainless steel inhibit considerably the thermal release rate of tritium.

• OSTI ID: 22429780
• Journal Information: Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 3 Vol. 67; ISSN 1536-1055
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ARGON
AUSTENITIC STEELS
DIFFUSION
FIRST WALL
ITER TOKAMAK
ONE-DIMENSIONAL CALCULATIONS
STAINLESS STEELS
TEMPERATURE DEPENDENCE
TEMPERATURE RANGE 0400-1000 K
TRITIUM
TRITIUM OXIDES