Testing and analysis of coupled program of MCNP and FISPACT

The burnup calculation of reactors is related to the fuel management of the reactor, and directly affect the economic evaluation of the core, therefore how to calculate burnup characteristics of reactors faster and better is an important part of the research. With the development of the reactor, its geometry becomes more and more complex. Some of the existing one-dimensional or two-dimensional burnup coupled program, due to restrictions on the geometry processing, are difficult to meet the requirements of advanced reactors design and analysis. In this paper, we combine the advantages of MCNP which is good at dealing with complex geometry, and FISPACT which could process radionuclides very comprehensively. The FISPACT and MCNP were coupled for burnup calculation, and the coupled program was verified by calculating the examplesIAEA ADS-benchmark and fusion reactor example. The calculation results of keff and tritium breeding ratio(TBR) by the coupled program are in good agreement with the standard results, and the errors are within acceptable ranges.