&nbsp;&nbsp;&nbsp;&nbsp;&nbsp; SuperCritical Water (SCW) is widely used in advanced coal-fired power plants around the world with the main objective to increase thermal efficiency of the Rankine cycle from ~43% at subcritical pressures to about 55% at SuperCritical Pressures (SCPs). &nbsp;However, 96% of modern Nuclear Power Plants (NPPs) equipped with subcritical-pressure light- and heavy-water-cooled reactors have significantly lower thermal efficiencies (30‒36% (up to 38% for Generation III+ reactors)) compared to those of advanced thermal power plants.&nbsp; Therefore, increasing thermal efficiency of these NPPs is a very important task.&nbsp;&nbsp;&nbsp;&nbsp; SuperCritical Water-cooled Reactor (SCWR) is a Generation-IV nuclear-reactor concept. &nbsp;The main advantage of NPPs with SCWRs will be higher thermal efficiencies (at least 45%). &nbsp;Currently, there are some ideas to develop Small Modular Reactors (SMRs) at SCPs.&nbsp; Therefore, for safe and reliable operation of future SCWRs more experimental data are required in bundle-flow geometries cooled with SCW. &nbsp;However, such experiments are extremely complicated and expensive.&nbsp; Therefore, as a preliminary, but a universal approach, experimental data obtained in vertical bare tubes with diameters similar to those of fuel bundles cooled with SCW are used.&nbsp;&nbsp;&nbsp;&nbsp;Current paper provides new experimental data obtained in a short (1-m) vertical bare tube (ID 10 mm) cooled with upward flow of SCW. &nbsp;Analysis of this dataset is included.

Study on Deteriorated Heat Transfer in Upward Flow of Supercritical Water in a 1-M Vertical Bare Tube

Paper Proceedings: https://asmedigitalcollection.asme.org/ICONE/ICONE28/volume/85246

2021 28th International Conference on Nuclear Engineering (ICONE28)

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