Abstract: The present work aims at the curved structure of coolant flow channel and corresponding operation conditions in the subcritical energy blanket of fusion-fission hybrid reactor. The critical heat flux（CHF） model is established for the local inclined channel and corresponding code is developed. Then the model is verified with experimental data under both vertical and inclined conditions. The results show that the present model has good prediction accuracy in a wide parameter range. After that, the local inclination effect on CHF is investigated using the developed code. The results show that with the increasing of the local inclination angle and worsening thermal-hydraulic conditions, the CHF ratio of local-inclined to vertical flow channel decreases.