International Thermonuclear Experimental Reactor (ITER) divertor plate performance and lifetime considerations
Abstract
The ITER divertor plate performance during the technology phase of operation has been analyzed. High-Z materials, such as tungsten and tantalum, have been considered as plasma side materials, and refractory metal alloys, Ta-10W, TZM, Nb-1Zr, and V-15Cr-5Ti, plus copper alloys have been considered as the structural materials. The fatigue lifetime have been predicted for structural plates and for duplex plates with the plasma side material bonded to the structure. The results indicate that refractory alloys have a comparable or improved performance to copper alloys. Peak allowable heat fluxes for these analyses are in the range of 15--20 MW/m{sup 2} for 2 mm thick structural plates and 7--11 MW/m{sup 2} for 4 mm thick duplex plates. 4 refs., 55 figs., 6 tabs.
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab., IL (USA). Fusion Power Program
- Sponsoring Org.:
- DOE/ER
- OSTI Identifier:
- 6938320
- Report Number(s):
- ANL/FPP/TM-246
ON: DE90010277; TRN: 90-014505
- DOE Contract Number:
- W-31109-ENG-38
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DIVERTORS; PERFORMANCE; THERMONUCLEAR REACTOR MATERIALS; MATERIALS TESTING; FATIGUE; ITER TOKAMAK; LIFETIME; MECHANICAL PROPERTIES; TANTALUM BASE ALLOYS; TUNGSTEN BASE ALLOYS; ALLOYS; CLOSED PLASMA DEVICES; MATERIALS; TANTALUM ALLOYS; TESTING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; TUNGSTEN ALLOYS; 700202* - Fusion Power Plant Technology- Magnet Coils & Fields; 700209 - Fusion Power Plant Technology- Component Development & Materials Testing
Citation Formats
Mattas, R F. International Thermonuclear Experimental Reactor (ITER) divertor plate performance and lifetime considerations. United States: N. p., 1990.
Web. doi:10.2172/6938320.
Mattas, R F. International Thermonuclear Experimental Reactor (ITER) divertor plate performance and lifetime considerations. United States. https://doi.org/10.2172/6938320
Mattas, R F. 1990.
"International Thermonuclear Experimental Reactor (ITER) divertor plate performance and lifetime considerations". United States. https://doi.org/10.2172/6938320. https://www.osti.gov/servlets/purl/6938320.
@article{osti_6938320,
title = {International Thermonuclear Experimental Reactor (ITER) divertor plate performance and lifetime considerations},
author = {Mattas, R F},
abstractNote = {The ITER divertor plate performance during the technology phase of operation has been analyzed. High-Z materials, such as tungsten and tantalum, have been considered as plasma side materials, and refractory metal alloys, Ta-10W, TZM, Nb-1Zr, and V-15Cr-5Ti, plus copper alloys have been considered as the structural materials. The fatigue lifetime have been predicted for structural plates and for duplex plates with the plasma side material bonded to the structure. The results indicate that refractory alloys have a comparable or improved performance to copper alloys. Peak allowable heat fluxes for these analyses are in the range of 15--20 MW/m{sup 2} for 2 mm thick structural plates and 7--11 MW/m{sup 2} for 4 mm thick duplex plates. 4 refs., 55 figs., 6 tabs.},
doi = {10.2172/6938320},
url = {https://www.osti.gov/biblio/6938320},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Mar 01 00:00:00 EST 1990},
month = {Thu Mar 01 00:00:00 EST 1990}
}