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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 |
Files in This Item:
File | Description | Size | Format | |
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Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs.pdf | 32.54 MB | Adobe PDF | View/Open |
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