The Breeding Blanket Interface (BBI): Recent results for the solid breeder and the aqueous salt solution blanket concepts

Conference · Sun Oct 01 00:00:00 EDT 1989

OSTI ID:5292447

Clemmer, R G; Finn, P A; Greenwood, L R; Sze, D K; Bartlit, J R; Sherman, R; Anderson, J L; Yoshida, H; Naruse, Y; Enoeda, M; Okuno, K ^[1]

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1. Argonne National Lab., IL (USA)

The Tritium Systems Test Assembly (TSTA) at Los Alamos is a full-scale facility dedicated to testing tritium processing for fusion reactors. We are involved in a study of adding a Breeder Blanket Interface (BBI) to the TSTA. The BBI is to test the processing required for the tritium output streams for the various fusion reactor breeder blankets. In the current phase of the study, we are evaluating the characteristics of the output from various breeding blankets types. Emphasis is placed on defining the output stream with respect to H/T ratio, impurity content, and radionuclide content. Reported herein is an assessment for two blanket concepts: solid breeder blanket (ceramic, Li{sub 2}O), and aqueous salt solution. 24 refs., 2 figs., 2 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/ER; JAERI
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5292447
• Report Number(s): CONF-891007-100; ON: DE90003808; TRN: 90-000257
• Resource Relation: Conference: 13. IEEE symposium on fusion engineering, Knoxville, TN (USA), 2-6 Oct 1989
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
THERMONUCLEAR REACTORS
BREEDING BLANKETS
IMPURITIES
LITHIUM OXIDES
TESTING
TRITIUM SYSTEMS TEST ASSEMBLY
ALKALI METAL COMPOUNDS
CHALCOGENIDES
LITHIUM COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
TEST FACILITIES
700201* - Fusion Power Plant Technology- Blanket Engineering