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Volumn 29, Issue 16, 2002, Pages 1871-1889

Neutronic analysis of PROMETHEUS reactor fueled with various compounds of thorium and uranium

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; FISSION PRODUCTS; FUSION REACTIONS; HELIUM; NUCLEAR ENERGY; NUCLEAR FUELS; RESONANCE; SILICON CARBIDE; THORIUM; URANIUM;

EID: 0036832934     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(02)00016-6     Document Type: Article
Times cited : (34)

References (58)
  • 33
    • 0024650227 scopus 로고
    • Power flattening in a hybrid blanket using nuclear waste actinides
    • (1989) Kerntechnik , vol.53 , pp. 285
    • Şahin, S.1
  • 38
    • 0024769818 scopus 로고
    • Investigation of the neutronic potential of moderated and fast (D, T) hybrid blankets for rejuvenation of CANDU spent fuel
    • (1989) Fusion Technology , vol.16 , pp. 331
    • Şahin, S.1    Yapici, H.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.