METHODS OF XS DATA PREPARATION FOR GEOMETRY WITH FUEL DUMMY

Authors

DOI:

https://doi.org/10.14311/APP.2020.28.0023

Keywords:

Eigenvalue, flux, fuel dummy, homogenization, SCALE, Serpent, PARCS

Abstract

3D deterministic core calculation represents important category of the nuclear fuel cycle and safe Nuclear Power Plant operation. The appropriate solution was not published yet. Data preparation process for non-fuel elements of the core represents the challenge for scientists. This report briefly introduce the problem of the data preparation process and gives the information about new input format for macrocode PARCS (PMAXS). The best homogenization process approach is to prepare data in infinite lattice cell for fuel assemblies, which are placed next to the another fuel assembly. Data for fuel assembly located next to the non-fuel region are better with preparation in the real geometry with the real boundary conditions. Results of the neutron spectra study show that the PMAXS file format is well prepared for the 2 group calculation, but it is not well prepared for the multigroup calculations, however the XSEC file format still gave reasonable results.

Author Biography

Pavel Suk, Czech Technical University in Prague, Czech Republic

Czech Technical University in Prague, Faculty of Nuclear Science and Physical Engineering, Department of
Nuclear Reactors, V Holešovickách 2, 180 00 Prague 8, Czech Republic

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Published

2020-12-01