Benchmark test of JEFF-3.2, FENDL-3.0 and TENDL-2015 with TOF experiments for graphite, silicon carbide, uranium and multiple-slab samples

In order to validate JEFF-3.2, FENDL-3.0 and TENDL-2015 nuclear data libraries, some integral experiments have been conducted with TOF method on the D-T neutron source facility at China Institute of Atomic Energy (CIAE). The measured neutron spectra for Silicon Carbide, Graphite, Uranium and multi-slab sample assemblies were compared with the leakage neutron spectra simulated using the MCNP-4C code with the evaluated nuclear data libraries. The comparison was made by the spectrum shape and the C/E values in five energy regions. From the results we can conclude that all the calculations reproduce well the measurements except at a few neutron energy ranges. It is worth mentioning that the calculated results with FENDL-3.0 are almost the same as those with TENDL-2015for graphite. And compared to JEFF-3.1.1, the nuclear data of carbon were not revised in JEFF-3.2. An interesting phenomenon was significantly observed from the results of multi-slab sample assemblies. The excessive number of elastically-scattered neutrons in the U layer are moderated by the hydrogen in the last layer to lower energies as the C/E ratio satisfactorily becomes consistent with 1.0.