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Advanced CANDU reactors axial xenon oscillation controllability validation

Advanced CANDU reactor fuel channel assembly MCNP model with top, bottom, and four lattice sides reflecting boundaries is used to generate a conservative flat axial neutron flux distribution for the 135Xe oscillation controllability analyses. Burnup-dependent neutron Fission Tally and 135Xe axial pr...

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Bibliographic Details
Published in:Annals of nuclear energy 2016-10, Vol.96, p.441-445
Main Author: Chang, G.S.
Format: Article
Language:English
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Summary:Advanced CANDU reactor fuel channel assembly MCNP model with top, bottom, and four lattice sides reflecting boundaries is used to generate a conservative flat axial neutron flux distribution for the 135Xe oscillation controllability analyses. Burnup-dependent neutron Fission Tally and 135Xe axial profiles are calculated using the Monte Carlo burnup script MCOS. The controllability of the 135Xe oscillations is validated by the MCOS-calculated xenon reactivity worth swings with respect to the mean. The validated upper bound of the xenon reactivity swing band of ±3mk is well within the zone controller reactivity bank of ±7mk.
ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2016.06.039