Development of Sodium Fire Analysis Code Capabilities for Versatile Test Reactor

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Abstract

Because the Versatile Test Reactor (VTR) uses sodium as a primary and secondary coolant, an analysis of postulated sodium leaks that could result in sodium fires is needed for VTR safety analysis. The goals of such an analysis include, among other topics, determination of temperature and pressure loadings on the reactor building from sodium fires. This paper provides a description of sodium spray and pool fire analysis tool development at Argonne National Laboratory for application to the VTR and includes validation against available data from sodium fire experiments.

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Moisseytsev, A., Bucknor, M., & Sienicki, J. J. (2022). Development of Sodium Fire Analysis Code Capabilities for Versatile Test Reactor. Nuclear Science and Engineering, 196(sup1), 323–336. https://doi.org/10.1080/00295639.2021.2018925

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