Please use this identifier to cite or link to this item: http://elibrary.nnra.gov.ng/jspui/handle/123456789/622
Title: Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs)
Authors: IAEA
Keywords: Water cooled reactors
Nuclear reactors — Thermodynamics.
Thermal hydraulics.
Issue Date: 2020
Publisher: NNRA Library
Series/Report no.: TECDOC-1900;
Description: he present publication provides the background and objectives of the CRP; descriptions of a revised Canadian SCWR design concept and a new SCWR design concept being developed at the Nuclear Power Institute of China; updated information on key technology areas (e.g. heat transfer in simple geometries, stability and critical flow) obtained since the completion of the previous CRP; new experiments and data on supercritical heat transfer in bundles and on critical heat flux; and application of the direct numerical simulation approach for supercritical heat transfer.
URI: http://elibrary.nnra.gov.ng/jspui/handle/123456789/622
Appears in Collections:Nuclear Power



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