A European proposal for a ITER water cooled solid breeder blanket
- NET, Garching (Germany)
- CFFTP, Mississauga, Ontario (Canada)
- ENEA, Frascati (Italy)
The Water Cooled Solid Breeder Blanket concept here proposed is based on a conservative approach, involving well proven technologies and-qualified materials. 316 L type stainless steel has been selected as the structural material. The nominal performances are: 1 MW/m{sup 2} as the average neutron wall load which corresponds to a fusion power of about 1.5 GW, and 1 MWy/m{sup 2} as the average neutron fluence. The power margins of the proposed concept have been estimated. The proposed blanket concept is based on a Breeder Inside Tube (BIT) type blanket with poloidal breeding elements, whose dimensions are compatible with space available in test fission reactor core channels, that makes easier in-pile testing required for the blanket development and qualification. Each breeding element consists of two concentric tubes. 1.2 mm lithium metazirconate (Li{sub 2}ZrO{sub 3}) pebbles are filled into the inner tube, the water coolant flows in the annular channel between the two tubes, and 2 mm Beryllium pebbles are poured into the blanket box outside the outer tube. Lithium metazirconate has been selected as the breeder material because it presents today the best tritium release properties at low temperature. A helium purge gas flows through the breeder pebble bed for tritium recovery. A Shielding Blanket can be derived from the proposed Blanket concept by removing the breeder pebbles from the inner tube. In-situ convertibility issues are addressed.
- OSTI ID:
- 196998
- Report Number(s):
- CONF-940664--
- Country of Publication:
- United States
- Language:
- English
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