Coupling between ANISN-Br and citation programs for burnup calculations of fast micro-reactor

The coupling between the ANISN-Br and Citation codes to study the fuel burnup of very high temperature (T∼1300 K) fast micro-reactor (Pthermal < 1.2 MW) is reported. A problem in reactor burnup calculation is the evaluation of the fission products (FP) effects in core reactivity. A pre-processing nuclear data subroutine was introduced in the ANISN-Br code to enable the use of effective microscopic cross section of lumped FP of the Japanese Fast Set (JFS-II) library. Another improvement was the introduction of an interface module to condense microscopic cross sections in suitable format to be used by Citation code in burnup studies. The new capabilities were evaluated with the calculation of the Japanese experimental fast reactor Joyo MK-I assembly macro cell. The results show that the modifications are working as expected. (author)