Liquid metal blanket module testing and design for ITER/TIBER II
A major goal for ITER is the testing of nuclear components to demonstrate the integrated performance of the most attractive concepts that can lead to a commercial fusion reactor. As part of the ITER/TIBER II study, the test program and design of test models were examined for a number of blanket concepts. The work at Argonne National Laboratory focused on self-cooled liquid metal blankets. A test program for liquid metal blankets was developed based upon the ITER/TIBER II operating schedule and the specific data needs to resolve the key issues for liquid metals. Testing can begin early in reactor operation with liquid metal MHD tests to confirm predictive capability. Combined heat transfer/MHD tests can be performed during initial plasma operation. After acceptable heat transfer performance is verified, tests to determine the integrated high temperature performance in a neutron environment can begin. During the high availability phase operation, long term performance and reliability tests will be performed. It is envisioned that a companion test program will be conducted outside ITER to determine behavior under severe accident conditions and upper performance limits. A detailed design of a liquid metal test module and auxiliary equipment was also developed. The module followed the design of the TPSS blanket. Detailed analysis of the heat transfer and tritium systems were performed, and the overall layout of the systems was determined. In general, the blanket module appears to be capable of addressing most of the testing needs. 8 refs., 27 figs., 11 tabs.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6966452
- Report Number(s):
- ANL/FPP/TM-222; ON: DE88014688
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
DESIGN
TESTING
TIBER-X TOKAMAK
CORROSION
FIRST WALL
HEAT TRANSFER
HYDRAULICS
PLASMA DISRUPTION
SHIELDING
STRESS ANALYSIS
TEMPERATURE DISTRIBUTION
THERMONUCLEAR REACTOR MATERIALS
TRITIUM RECOVERY
CHEMICAL REACTIONS
ENERGY TRANSFER
FLUID MECHANICS
MATERIALS
MECHANICS
REACTOR COMPONENTS
RECOVERY
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700201* - Fusion Power Plant Technology- Blanket Engineering