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BN-600 Full MOX Core Benchmark Analysis

Abstract : As a follow-up of the BN-600 hybrid core benchmark, a full MOX core benchmark was performed within the framework of the IAEA co-ordinated research project. Discrepancies between the values of main reactivity coefficients obtained by the participants for the BN-600 full MOX core benchmark appear to be larger than those in the previous hybrid core benchmarks on traditional core configurations. This arises due to uncertainties in the proper modelling of the axial sodium plenum above the core. It was recognized that the sodium density coefficient strongly depends on the core model configuration of interest (hybrid core vs. fully MOX fuelled core with sodium plenum above the core) in conjunction with the calculation method (diffusion vs. transport theory). The effects of the discrepancies revealed between the participants’ results on the ULOF and UTOP transient behaviours of the BN-600 full MOX core were investigated in simplified transient analyses. Generally the diffusion approximation predicts more benign consequences for the ULOF accident but more hazardous ones for the UTOP accident when compared with the transport theory results. The heterogeneity effect does not have any significant effect on the simulation of the transient. The comparison of the transient analyses results concluded that the fuel Doppler coefficient and the sodium density coefficient are the two most important coefficients in understanding the ULOF transient behaviour. In particular, the uncertainty in evaluating the sodium density coefficient distribution has the largest impact on the description of reactor dynamics. This is because the maximum sodium temperature rise takes place at the top of the core and in the sodium plenum.
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Submitted on : Wednesday, August 19, 2020 - 3:16:44 PM
Last modification on : Thursday, August 20, 2020 - 3:15:52 AM

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  • HAL Id : cea-02917608, version 1

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Kim Y. I., Hill R., Grimm K., Rimpault G., Newton T., et al.. BN-600 Full MOX Core Benchmark Analysis. PHYSOR 2004 -The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, American Nuclear Society, Apr 2004, Chicago, Illinois, United States. ⟨cea-02917608⟩

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