Preliminary Validation Studies of Existing Neutronics Analysis Tools for Advanced Burner Reactor Design Applications

Yang, Won Sik; Kim, T. K.; Kim, S. J.; Lee, C. H.

doi:10.2172/1508296

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Sodium Void Worth1

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2023

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Cited by 2 publications

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“…Additionally, the calculations performed here applied the ENDF/B-VII.1 cross section library, whereas other studies in the literature used much older nuclear data libraries. According to [31], for both homogeneous and heterogeneous models, older libraries, like ENDF/B-V, can lead to a positive sodium void worth; conversely, newer ENDF/B-VI and ENDF/B-VII.0 libraries can result in a negative worth for the same configuration.…”

Section: Sodium Void Worthmentioning

confidence: 99%

SCALE Modeling of the Sodium Cooled Fast-Spectrum Advanced Burner Test Reactor

Shaw,

Bostelmann,

Hartanto

et al. 2023

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Various reactivity calculations were performed with SCALE for the ABTR and, where possible, compared with results available in the open literature. Additionally, SCALE was used to perform a full-core depletion calculation over the 4 month cycle to obtain the nuclide inventory at the end of equilibrium cycle (EOEC). These nuclide inventories, decay heat, power profiles, and reactivity feedback coefficients at EOEC represent the initial conditions for analyzing severe accident scenarios with MELCOR.

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Section: Sodium Void Worthmentioning

confidence: 99%