Development of a method to treat the energy variable in neutron transport calculations based on Discrete Wavelet Transform

Yuya Suzuki

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[1K07-08] Analysis Method 3

Mon. Mar 13, 2023 2:45 PM - 3:20 PM Room K (13 Bildg.2F 1322)

Chair:Tomoaki Watanabe(JAEA)

2:45 PM - 3:00 PM

[1K07] Development of a method to treat the energy variable in neutron transport calculations based on Discrete Wavelet Transform

*Yuya Suzuki¹, Willem van Rooijen¹ (1. University of Fukui)

Keywords:Cross sections, Self-shielding effectiveness evaluation, Discrete Wavelet Transform, Transport theory, Non-homogeneous systems

Optimized energy meshes by using discrete wavelet transforms to handle energy variables in cross sections. A new approach to cross section processing by discrete wavelet transform in non-homogeneous systems is developed.