Modeling the spectral history in the depletion of a PWR core.


Modeling the spectral history in the depletion of a PWR core.

Bilodid, I.

Codes for reactor core calculations use few-group cross sections (XS) which depend on local burnup, given in terms of the energy produced per fuel mass (MWd/kgHM). However, a certain burnup value can be reached under different spectral conditions depending on moderator density and other local parameters. Neglecting these spectral effects, i.e. applying the summary-burnup value only, can cause considerable errors in the calculated power density.
This paper describes a way to take into account spectral-history effects. It is shown that the respective XS correction linearly depends on the actual Pu-239 concentration. The applicability of the method was proved not only for usual uranium oxide fuel, but also for mixed uranium/plutonium oxide (MOX) and fuel assemblies with burnable absorber. The code DYN3D was extended by new subroutines which calculate the actual distribution of Pu-239 in the core and apply a spectral-history correction for the XS.

Keywords: cross section library; history effects; spectral history; burnup; DYN3D

  • Contribution to proceedings
    18th International Conference on Nuclear Engineering (ICONE18), 17.-21.05.2010, Xi'an, China
    Proceedings of the 18th International Conference on Nuclear Engineering (ICONE18) May 17-21, 2010 • Xi’an, China
  • Poster
    18th International Conference on Nuclear Engineering (ICONE18), 17.-21.05.2010, Xi'an, China
  • Lecture (Conference)
    18th International Conference on Nuclear Engineering (ICONE18), 17.-21.05.2010, Xi'an, China

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Publ.-Id: 14073