Performance simulation of fusion-fission hybrid blanket concepts in existing fission test facilities

Conference · Thu Jan 01 04:00:00 EST 1981

OSTI ID:5154250

Hsu, P Y; Deis, G A; Miller, L G; Moir, R W; Lee, J D; Maniscalco, J A; Berwald, D H

This paper examines the usefulness of testing hybrid fusion-fission blanket components in fission reactors, and reports the results of calculations indicating that blanket heating profiles, tritium breeding rates, fertile breeding rates, and fast-fission rates can be accurately duplicated in a fission reactor test. These results indicate that fission testing can play a major part in the hybrid blanket development program.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA); Lawrence Livermore National Lab., CA (USA); TRW Systems, Redondo Beach, CA (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5154250
• Report Number(s): EGG-M-05182; CONF-820406-14; ON: DE82017734
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BARYON REACTIONS
BREEDING BLANKETS
HADRON REACTIONS
HEATING
HYBRID REACTORS
HYBRID SYSTEMS
NEUTRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
PERFORMANCE TESTING
RADIATION HEATING
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
TEST REACTORS
TESTING