Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs)

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DC Field	Value	Language
dc.contributor.author	IAEA	-
dc.date.accessioned	2021-03-24T09:19:58Z	-
dc.date.available	2021-03-24T09:19:58Z	-
dc.date.issued	2020	-
dc.identifier.uri	http://elibrary.nnra.gov.ng/jspui/handle/123456789/622	-
dc.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.	en_US
dc.language.iso	en	en_US
dc.publisher	NNRA Library	en_US
dc.relation.ispartofseries	TECDOC-1900;	-
dc.subject	Water cooled reactors	en_US
dc.subject	Nuclear reactors — Thermodynamics.	en_US
dc.subject	Thermal hydraulics.	en_US
dc.title	Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs)	en_US
dc.type	Book	en_US
Appears in Collections:	Nuclear Power

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