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

Conference · Thu Jan 01 00:00:00 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
• Resource Relation: Conference: Topical meeting on fast, thermal and fusion reactor experiments, Salt Lake City, UT, USA, 12 Apr 1982
• Country of Publication: United States
• Language: English

Related Subjects

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