Modeling of tritium behavior in Li{sub 2}O
Technical Report
·
OSTI ID:10174704
The TIARA and DISPL2 codes are being developed at Argonne National Laboratory to predict tritium retention and release from lithium ceramics under steady-state and transient conditions, respectively. Tritium retention and release are important design and safety issues for tritium-breeding blankets of fusion reactors. Emphasis has been placed on tritium behavior in Li{sub 2}O because of the selection of this ceramic as a first option for the ITER driver blanket and because of the relatively good material properties data base for Li{sub 2}O. Models and correlations for diffusion, surface desorption/adsorption, and solubility/precipitation of tritium in Li{sub 2}0 have been developed based on well-controlled laboratory data from as-fabricated and irradiated samples. With the models and correlations, the codes are validated to the results of in-reactor purge flow tests. The results of validation of TIARA to tritium retention data from VOM-15H, EXOTIC-2, and CRITIC-1 are presented, along with predictions of tritium retention in BEATRIX-II. For DISPL2, results are presented for tritium release predictions vs. data for MOZART, CRITIC-1, and BEATRIX-II. Recommendations are made for improving both the data base and the modeling to allow extrapolation with reasonable uncertainty levels to fusion reactor design conditions.
- Research Organization:
- Argonne National Lab., IL (United States). Fusion Power Program
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10174704
- Report Number(s):
- ANL/FPP/TM--260; ON: DE92041358
- Country of Publication:
- United States
- Language:
- English
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