Cross-section uncertainty propagation in the multigroup slowing-down equations using probability table formalism

Journal Article · Sun Jan 15 04:00:00 EST 2012 · Nuclear Science and Engineering

DOI:https://doi.org/10.13182/NSE10-94TN· OSTI ID:22273983

Diop, Cheikh M.; Coste-Delclaux, Mireille; Lahaye, Sebastien ^[1]

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1. CEA Saclay, Serv Etud Reacteurs et Math Appl, DEN DANS DM2S, Commissariat Energie Atom et Energies Alternat, F-91191 Gif Sur Yvette, (France)

In the frame of neutral-particle (neutron, gamma) transport, the uncertainty propagation calculation regarding the uncertainties on cross sections is often carried out without explicitly taking into account their probabilistic distribution. We investigate a new uncertainty propagation formalism where the cross-section uncertainty distributions are represented by probability tables. This technical note develops this approach for the steady-state slowing-down equation without up-scattering and in an infinite medium. This work is based on a deterministic multiband formalism that takes into account multilevel probability tables for cross sections. The first level represents the variation of cross sections versus lethargy (or energy) in each group of the multigroup lethargy mesh and thus corresponds to the classical cross-section probability tables. The higher levels represent the uncertainties on each step of the first-level cross-section probability table. This method is validated against a Monte Carlo calculation in a case of neutron slowing down in a {sup 238}U-hydrogen homogeneous mixture, showing fully consistent numerical results. The main interest of the deterministic multilevel multiband formalism is that it gives not only the mean value and the variance but also a probabilistic distribution of the fluxes. In the near future, we plan to investigate more deeply the robustness of this new approach in relation to high values of cross-section uncertainties and to introduce cross-section uncertainty correlations as well. Meanwhile, the promise of this work is its extension to the general transport steady-state equation solved by the discrete ordinates (S(N)) or Monte Carlo methods. (authors)

• OSTI ID: 22273983
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 1 Vol. 170; ISSN 0029-5639
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CROSS SECTIONS
MONTE CARLO METHOD
NEUTRON TRANSPORT
SLOWING-DOWN
STEADY-STATE CONDITIONS