Tritium self-sufficiency and neutron shielding performance of self-cooled liquid blanket system for helical reactor

Fusion Science and Technology

Volumn 47, Issue 3, 2005, Pages 530-534

  Tanaka, Teruya ^a   Muroga, Takeo ^a   Sagara, Akio ^a  

^a NATIONAL INSTITUTE FOR FUSION SCIENCE   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

BERYLLIUM; COOLING; NEUTRONS; RADIATION SHIELDING; STEEL; VANADIUM ALLOYS;

HELICAL REACTORS; LIQUID BLANKET SYSTEM; NEUTRON MULTIPLIERS; TRITIUM BREEDING RATIO (TBR);

NUCLEAR REACTORS;

EID: 17544362461     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/FST05-A738     Document Type: Conference Paper

References (14)

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