Summary of the radiological assessment of the fuel cycle for a thorium-uranium carbide-fueled fast breeder reactor | Zendy

V.J. Tennery | Zendy; E.S. Bomar | Zendy; W.D. Bond | Zendy; H.R. Meyer | Zendy; L. E. Morse | Zendy; John E. Till | Zendy; M.G. Yalcintas | Zendy

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Summary of the radiological assessment of the fuel cycle for a thorium-uranium carbide-fueled fast breeder reactor

Author(s) -

V.J. Tennery,

E.S. Bomar,

W.D. Bond,

H.R. Meyer,

L. E. Morse,

John E. Till,

M.G. Yalcintas

Publication year - 1980

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/711007

Subject(s) - fissile material , thorium , uranium , nuclear engineering , breeder reactor , environmental science , thorium fuel cycle , waste management , plutonium , fuel cycle , spent nuclear fuel , radiochemistry , breeder (animal) , radiological weapon , uranium 233 , materials science , metallurgy , mox fuel , chemistry , engineering , nuclear physics , neutron , physics , blanket , composite material

A large fraction of the potential fuel for nuclear power reactors employing fissionable materials exists as ores of thorium. In addition, certain characteristics of a fuel system based on breeding of the fissionable isotope {sup 233}U from thorium offer the possibility of a greater resistance to the diversion of fissionable material for the fabrication of nuclear weapons. This report consolidates into a single source the principal content of two previous reports which assess the radiological environmental impact of mining and milling of thorium ore and of the reprocessing and refabrication of spent FBR thorium-uranium carbide fuel

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