Development of 3d reactor burnup code based on monte carlo method and exponential euler method

Burnup analysis plays a key role in fuel breeding,transmutation and post-processing in nuclear reactor.Burnup codes based on one-dimensional and two-dimensional transport method have difficulties in meeting the accuracy requirements.A three-dimensional burnup analysis code based on Monte Carlo method and Exponential Euler method has been developed.The coupling code combines advantage of Monte Carlo method in complex geometry neutron transport calculation and FISPACT in fast and precise inventory calculation,meanwhile resonance Self-shielding effect in inventory calculation can also be considered.The IAEA benchmark text problem has been adopted for code validation.Good agreements were shown in the comparison with other participants' results.