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In transition: Commercializing fusion power
Commercial fusion power is closer than ever. There are now around 30 U.S. fusion companies, several of which claim to be on track to connect to the grid as early as the 2030s.
Tokamak and laser inertial confinement approaches benefit from decades of research at facilities such as the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory and ITER, with alternative concepts including stellarator, magnetic mirror, and Z-pinch confinement also making notable progress as private and government funding for fusion increases.
M. Ishii, H. K. Fauske
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 131-146
Technical Paper | doi.org/10.13182/NSE83-A17719
Articles are hosted by Taylor and Francis Online.
For certain postulated severe accident conditions such as a loss of piping integrity and a loss of heat sink in connection with liquid-metal fast breeder reactor safety analysis, the process of decay heat removal can lead to coolant boiling. For such low-heat-flux/low-flow conditions, a dryout or critical heat flux criterion is required in order to assess the potential for fuel pin failure and melting. Computer codes and full-scale experimental data are not available to completely address this problem at this time. Based on the interpretation of available experimental data and new analyses, it is concluded that a typical subassembly can be safely cooled (avoid dryout) under natural convection conditions for heat fluxes below ∼8 to 10% of the average nominal power; i.e., decay heat power levels can be safely accommodated in the natural convective regime. Furthermore, since this coolability limit is predicted to be rather insensitive to the subcooling value, it follows that the safety case relative to decay heat removal for an intact core geometry also becomes essentially independent of detailed accident conditions such as the potential for temporary stagnated flow or inlet flow reversal conditions.