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A coupled thermal-nonlinear hydraulic-mechanical (THM) model for fault water inrush was carried out in this paper to study the water-rock-temperature

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Nuclear Engineering and Design 236 (2006) 295–308Quantitative assessment of thermal–hydraulic codes used for heavywater reactor calculationsAndrej Proˇ sek

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Experimental studies of Pb-Bi-Water direct contact boiling two-phase flow ASME. International Conference on Nuclear Engineering, Volume 2: Thermal

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Water Cooled Reactor (SCWR) concept, the IAEA launched the second (CRP) on thermal-hydraulics of SCWRs, entitled “Understanding and