Neutron physics analysis of thermionic reactors with U-233 as fuel and beryllium as moderator

Makaleler > Tam Makale · 1976

Yazarlar: Sümer Şahi̇n

Annals of Nuclear Energy, Uluslararası, 1976, cilt 3, ss 447-450

DOI: 10.1016/0306-4549(76)90029-3

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