Advanced CANDU reactors axial xenon oscillation controllability validation

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• 作者：G.S. Chang¹ ; ^{gray.chang@gmail.com" class="auth_mail" title="E-mail the corresponding author}
• 关键词：ACR-1000 ; advanced CANDU reactors ; AD ; atomic density (atoms/b-cm) ; L/A ; axial tally local to average ratio ; FCA ; fuel channels assembly ; MCOS ; MCNP Coupling with ORIGEN2-Script ; Fission Tally ; MCNP neutron fission flux tally ; XS ; nuclide cross-sections ; 1σ ; one standard deviation ; mk ; reactivity worth milli-K (10&minus ; 3) ; SAFP ; strong absorber fission products ; Xe-Δρ ; xenon reactivity
• 刊名：Annals of Nuclear Energy
• 出版年：2016
• 出版时间：October 2016
• 年：2016
• 卷：96
• 期：Complete
• 页码：441-445
• 全文大小：820 K

文摘

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 ±3 mk is well within the zone controller reactivity bank of ±7 mk.