Nuclear Engineering Department, Xi'an Jiaotong University, Xi'an 710049;
Nuclear Engineering Department, Xi'an Jiaotong University, Xi'an 710049;
Nuclear Engineering Department, Xi'an Jiaotong University, Xi'an 710049;
Nuclear Engineering Department, Xi'an Jiaotong University, Xi'an 710049;
transmission probability method; triangle mesh; neutron integral transport equation; unstructured fuel geometry; MCNP code;