Neutronic analyses of port impact on blankets and superconducting coils of CFETR
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DOI: 10.1016/j.fusengdes.2020.112165
Abstract: Abstract Chinese Fusion Engineering Test Reactor (CFETR) is an ITER-like test superconducting TOKAMAK fusion reactor. In CFETR, blankets face core plasma directly and are in charge of tritium breeding and neutron shielding, while the condition… read more here.
Keywords: blankets superconducting; port impact; neutronic analyses; impact blankets ... See more keywords