Tritium in the DIII-D carbon tiles
The amount of tritium in the carbon tiles used as a first wall in the DIII-D tokamak was measured recently when the tiles were removed and cleaned. The measurements were made as part of the task of developing the appropriate safety procedures for processing of the tiles. The surface tritium concentration on the carbon tiles was surveyed and the total tritium released from tile samples was measured in test bakes. The total tritium in all the carbon tiles at the time the tiles were removed for cleaning is estimated to be 15 mCi and the fraction of tritium retained in the tiles from DIII-D operations has a lower bound of 10%. The tritium was found to be concentrated in a narrow surface layer on the plasma facing side of the tile, was fully released when baked to 1,000{degree}C, and was released in the form of tritiated gas (DT) as opposed to tritiated water (DTO) when baked.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC03-89ER51114
- OSTI ID:
- 10173350
- Report Number(s):
- GA-A-21329; CONF-9306191-2; ON: DE93017417; TRN: 93:016717
- Resource Relation:
- Conference: International Atomic Energy Agency (IAEA) technical committee meeting on developments in fusion safety,Ontario (Canada),7-11 Jun 1993; Other Information: PBD: Jun 1993
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
TRITIUM
RADIOECOLOGICAL CONCENTRATION
FIRST WALL
CONTAMINATION
DOUBLET-3 DEVICE
GRAPHITE
CLEANING
REMOVAL
SAFETY
HEATING
INVENTORIES
OPERATION
HEAVY WATER
TRITIUM COMPOUNDS
RADIOACTIVITY
MATERIALS HANDLING
MONITORING
700420
700460
PLASMA-FACING COMPONENTS
HEATING AND FUELING SYSTEMS
FUELS