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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Latest News
DOE issues RFQ for clean-energy projects at WIPP
The Department of Energy has issued a request for qualifications (RFQ) for interested parties that are looking to establish carbon pollution–free electricity (CFE) projects at its Waste Isolation Pilot Plant site in New Mexico.
H. J. Uitslag-Doolaard, F. Alcaro, F. Roelofs, K. Zwijsen (NRG)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 945-954
The description of the “Dissymmetric Test” performed in the Phénix sodium fast reactor has recently become available as a blind benchmark for thermal-hydraulic modelling within the H2020 SESAME project. The transient consists of a largely asymmetric temperature distribution in the sodium pool resulting from a pump trip in one of the two intermediate circuits, followed by a reactor scram. Although this transient is particularly suitable to validate a 3-D Computational Fluid Dynamics (CFD) model of the thermal-hydraulics in the sodium pool, the computational cost of a relatively long transient analysis with a full-scope CFD model of the whole Phénix reactor system would be huge. The present paper describes the system thermal-hydraulic (STH) model and the multiscale approach adopted by NRG for the simulation of the Dissymmetric Test. The in-house STH code SPECTRA was used to model the complete primary and secondary sides (intermediate loops) and explicitly coupled with the CFD code ANSYS CFX. The latter was used to resolve the details of the flow distribution inside the sodium pools, as well as at the outlet window of the primary side of the intermediate heat exchangers. An STH stand-alone simulation of the transient was carried out for comparison.