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Simulation strategy for the evaluation of neutronic properties of a Canadian SCWR fuel channel

Geneviève Harrisson and Guy Marleau

Article (2013)

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The Canadian Supercritical-Water-Cooled Reactor (SCWR) is a vertical pressure tube reactor cooled with supercritical light water and moderated with heavy water. For normal operation, the local conditions of the coolant (density and temperature) and fuel (temperature) vary substantially along the channel. This means that to simulate adequately the behavior of the core under operating conditions or for anticipated accident scenario, expensive 3D transport calculations for a complete fuel channel are required. Here, we propose a simulation strategy that takes into account axial variations of the local conditions and avoids 3D transport calculations. This strategy consists in replacing the 3D simulation by a series of isolated 2D calculations followed by a single 1D simulation. It is shown that this strategy is efficient because the axial coupling along the fuel channel is relatively weak. In addition, the neutronic properties of a channel with axial reflector can be modeled using a simplified 3D transport calculation.

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TK1-9971; Article Subject; Electrical engineering. Electronics. Nuclear engineering

Subjects: 2400 Nuclear engineering > 2400 Nuclear engineering
2400 Nuclear engineering > 2401 Reactor design and operation
Department: Research Centres > Institut de génie nucléaire
Funders: CRSNG / NSERC - AECL Generation IV Energy Technologies Program, Fonds Québecois de la recherche sur la nature et les technologiques (FQRNT), Canadian Nuclear Society (CNS)
PolyPublie URL: https://publications.polymtl.ca/3446/
Journal Title: Science and Technology of Nuclear Installations (vol. 2013)
Publisher: Hindawi
DOI: 10.1155/2013/352757
Official URL: https://doi.org/10.1155/2013/352757
Date Deposited: 17 Jan 2019 13:57
Last Modified: 01 Nov 2023 12:52
Cite in APA 7: Harrisson, G., & Marleau, G. (2013). Simulation strategy for the evaluation of neutronic properties of a Canadian SCWR fuel channel. Science and Technology of Nuclear Installations, 2013, 1-10. https://doi.org/10.1155/2013/352757


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