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A parametrized diffusion cross section library was prepared for the HPLWR assembly with the MULTICELL neutronic transport code.
The 47-group BUGLE-96 neutron cross section library was used for construction of macroscopic neutron cross sections.
The WIMS-D5 with 69-group neutron cross section library, was used to calculate the five-group constants for different reactor regions essential to solve the diffusion equations.
For this, the Monte Carlo Serpent-2.27 code and the JEFF-3.1 cross section library were used to perform the calculations.
DeCART multi-group cross section library generation procedure based on the KAERI library generation system was improved using the new alternative procedures based on the Monte Carlo slowing down calculations.
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Cross section libraries were generated for the fast reactor analysis code ERANOS.
It was concluded that CNUREAS can be used for neutronic calculations of VVER type power reactors with appropriate cross section libraries and deterministic and Monte Carlo techniques give comparable results when both provided with appropriate cross section libraries.
Hayworth, K.J. et al. Imaging ATUM ultrathin section libraries with WaferMapper: a multi-scale approach to EM reconstruction of neural circuits.
The cross section libraries were generated using the lattice physics code WIMS9 (the commercial version of the legacy lattice code WIMSD).
The results were analyzed with the Monte Carlo neutron transport code MCNP-4C and several transport cross section libraries such as FENDL/MC-2.0.
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