Nuclear Steam-Reheat Options: World Experience
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Abstract
The paper overviews world experience in Nuclear Steam-Reheat (NSR). Calculations of heat transfer to a coolant (light water) at supercritical temperature and subcritical pressure (T = 400 – 625 °C, P = 5.7 – 6.1 MPa) in the Steam-Reheat Channels (SRCh) of the single-reheat cycle layout for the Super Critical Water-cooled Reactor (SCWR) proposed in [1] are presented. The sheath and fuel (UO2, UC, UC2) centerline temperatures are calculated at the cosine axial heat-flux profiles.
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