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- W1970824580 abstract "Abstract Most gas-cooled fast breeder reactor (GCFR) programs in Europe and the US are now coordinated and focused on a 300 MW(e) GCFR demonstration plant program. Except for venting and artificial surface roughening, GCFR fuel is similar to liquid metal fast breeder reactor (LMFBR) fuel and operates under nearly identical conditions. The primary helium system is integrated within a PCRV like all large gas-cooled thermal reactors, with three main loops and three auxiliary loops. Design and safety studies and various experiments, including heat transfer, irradiation, and critical experiments, indicate that most feasibility questions have been answered and a demonstration plant could be in operation within 12 years. This could be followed in the mid-1990s by a large-size GCFR with a doubling time of about 10 years fueled by (UO2PuO2) and producing either 233U in thorium blankets as fuel for advanced converters or plutonium in depleted uranium blankets." @default.
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- W1970824580 date "1977-01-01" @default.
- W1970824580 modified "2023-09-25" @default.
- W1970824580 title "Status of gas-cooled fast breeder reactor programs" @default.
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- W1970824580 doi "https://doi.org/10.1016/0029-5493(77)90147-9" @default.
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