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Volumn 29, Issue 3, 2002, Pages 287-302

Investigation of the flattened fissile fuel enrichment possibility with a (D, T) driven hybrid blanket cooled by flibe (Li2BeF4)

Author keywords

[No Author keywords available]

Indexed keywords

DEUTERIUM; FISSION REACTIONS; LITHIUM COMPOUNDS; NEUTRONS; NUCLEAR REACTORS; TRITIUM; URANIUM DIOXIDE;

EID: 0036462745     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(01)00038-X     Document Type: Article
Times cited : (9)

References (24)
  • 11
    • 0024769818 scopus 로고
    • Investigation of the neutronic potential of moderated and dast (D, T) hybrid blankets for rejuvenation of CANDU Spent Fuel
    • (1989) Fusion Technology , vol.16 , pp. 331
    • Şahin, S.1    Yapici, H.2
  • 13
    • 0025497858 scopus 로고
    • Power flattening in a catalyzed deuterium-deuterium fusion driven hybrid blanket using nuclear waste actinides
    • (1990) Nuclear Technology , vol.92 , pp. 93
    • Şahin, S.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.