Analysis of the three-dimensional VENUS-2 MOX core benchmark using the Monte Carlo code TRIPOLI-4 and the ENDF/B-VI.4, ENDF/B-VII.0 and JEFF-3.1 nuclear data sets

The reliability and verification of numerical solutions derived from neutronic codes and the use of nuclear data libraries is a very important issue in nuclear technology. To this purpose, computational benchmarks based on well-defined problems with a complete set of input and a unique solution, are often used. The OECD/NEA VENUS-2 is a widely used MOX benchmark problem for the validation of numerical methods and nuclear data sets. In this paper, the results of benchmarking the TRIPOLI Monte Carlo code based on the VENUS-2 MOX benchmark problem, are reported. 3-D TRIPOLI calculations were performed using the ENDF/B-VI.4, ENDF/B-VII.0 and JEFF-3.1 nuclear data sets. The computational results are compared with measured data, as well as with the results of other benchmark participants. In general the TRIPOLI results agree well with both the experimental data as well as those of other participants.