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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
Satoshi Nishio, Kichiro Shinya
Fusion Science and Technology | Volume 19 | Number 1 | January 1991 | Pages 86-94
Technical Paper | Plasma Engineering | doi.org/10.13182/FST91-A29318
Articles are hosted by Taylor and Francis Online.
A new method for mapping the plasma operational space of a tokamak reactor is proposed. The operational space within poloidal field (PF) coil engineering constraints is defined by three parameters, ψ, βp, and Ip, which are the magnetic flux supplied by the PF coil system, the poloidal beta, and the plasma current, respectively. It is also shown that the boundaries of the plasma operational space have a one-to-one correspondence with the PF coils. The design specifications of the PF coil system are thus related to the plasma operational space.
