Benchmark experiment on analytical mock-ups with graphite to simulate the fission blanket of hybrid reactor

To validate the nuclear data in evaluating the energy multiplication of neutronic concept of fusion fission hybrid, a new neutronics experiment has been designed and carried out. As a part of the series experiments, in this work, the fission rate study on the analytical mockups of Fission Blanket Assembly (FBA) with graphite (C) as reflector and with iron (Fe) as first wall was reported. The measurement was conducted with Plate Fission Chambers (PFC). The fissile material in the depleted uranium PFC is strictly the same as that in the mockups. The Monte Carlo calculation with MCNP5 and four libraries ENDF/BV.0, ENDF/B-VII.0, JENDL-3.3 and CENDL-3.1 was finished and compared with the experiment. The profile of fission rates in experiment agreed well with calculation. The calculation with JENDL-3.3 is sufficient to predict fission rates of depleted uranium in 10%. all calculated results of enriched uranium overestimate experimental ones when iron layer was added to the FBA/C assembly. The considerable discrepancy between the C/Es of Deu fission rates and Enu fission rates maybe caused by the neutron scattering data of uranium.