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Tada, Kenichi
Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet), 8 Pages, 2023/10
The number of energy grids of the thermal neutron scattering law data has a large impact on the data size of a cross section file of continuous energy Monte Carlo calculation codes. The optimization of the number of energy grids is an effective way to reduce the data size. This study developed the linearization method of the thermal neutron scattering cross section to optimize the number of energy grids and the linearization function was implemented in the nuclear data processing code FRENDY. The linearization process which is used in the resonance reconstruction and the Doppler broadening was adopted. The criticality benchmarks which use ZrH as the moderator were calculated to estimate the impact of the difference of the energy grids on neutronics calculations. The calculation results indicate that the linearization of the thermal neutron scattering cross section improves the prediction accuracy of neutronics calculations.
OKameda, Yasuo*; Sasaki, Motoya*; Usuki, Takeshi*; Otomo, Toshiya*; Ito, Keiji*; Suzuya, Kentaro; Fukunaga, Toshiharu*
Journal of Neutron Research, 11(3), p.153 - 163, 2003/09
We describe results of time-of-flight (TOF) neutron diffraction of the liquid water null-HO in order to investigate the effect of both the scattering angle and the neutron flight path ratio to the observed self-scattering intensities. An empirical inelasticity correction procedure is proposed using the self-scattering intensity observed for the null-HO.
Tada, Kenichi; Nagaya, Yasunobu
no journal, ,
JAEA has been developed the nuclear data processing system FRENDY (FRom Evaluated Nuclear Data librarY to any application). In this presentation, verification of scattering cross section generation in the thermal energy range is described.
Tada, Kenichi
no journal, ,
The nuclear data processing is very important to generate cross section libraries for neutronics calculation codes. Though many researchers want to generate cross section libraries by themselves, only few researchers can generate them. This presentation explains the processing flow and method of the nuclear data processing from evaluated nuclear data file into the cross section library. This presentation also explains how to generate cross section library from experimental data or analytical results of thermal neutron scattering.
