The small tokamak conceptual design based on the fusion-fission hybrid
reactor has been studied for a long time for breeding fuel and transm
utation of high level waste. If poloidal distributions of neutron wall
loading and flux are considered, the midplane equatorial port can be
used to test some components, such as blanket modules at a neutron wal
l loading of 1 MW m(-2) in a volume of 1.3 m x 1.3 m x 0.8 m, which ca
n satisfy preliminary requirements for testing some components in fusi
on environment.