Prediction of Reactor Pressure Tube Flow Transients with Effects of Friction and Heat Addition Included Using a Fixed-Grid Method of Characteristics

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dc.contributor.authorM.L. Gael
dc.contributor.authorD.J. Gorman
dc.date.accessioned2016-10-10T18:45:04Z
dc.date.available2016-10-10T18:45:04Z
dc.date.issued1975
dc.identifier.urihttp://www.lib.ncsu.edu/resolver/1840.20/28213
dc.publisherIASMiRT
dc.relation.ispartofseriesF - Structural Analysis of Reactor Core and Coolant Circuit Structures
dc.relation.ispartofseriesF1 - Dynamic Analysis of Reactor Core Structures
dc.relation.ispartofseriesSMiRT 3 - London, UK. 1975
dc.titlePrediction of Reactor Pressure Tube Flow Transients with Effects of Friction and Heat Addition Included Using a Fixed-Grid Method of Characteristics
dc.typeConference Proceeding

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1975 - SMiRT 3 - London, UK