Thermal hydraulic simulation of the triga ipr-r1 research reactor

dc.contributor.authorReis, P.A.L.en
dc.contributor.authorCosta, A.L.en
dc.contributor.authorPereira, C.en
dc.contributor.authorVeloso, M.A.F.en
dc.contributor.authorScari, M.E.en
dc.contributor.authorMiro, R.en
dc.contributor.authorVerdu, G.en
dc.date.accessioned2017-08-28T07:08:13Z
dc.date.available2017-08-28T07:08:13Z
dc.date.issued2016en
dc.descriptionPapers presented to the 12th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, Costa de Sol, Spain on 11-13 July 2016.en
dc.description.abstractThe safety analysis of research reactors includes simulations of selected cases classified by the International Atomic Energy Agency (IAEA), since the simulations are performed using validated nodalizations and internationally recognized, accepted and validated best estimate codes. The thermal-hydraulic analysis is considered as an essential aspect in the study of safety of nuclear reactors, since it can predict proper working conditions, steady-state and transient, thereby ensuring the safe operation of a nuclear reactor. A RELAP5 model verified for the IPR-R1 TRIGA research reactor was used here to study. A loss of coolant accident (LOCA) event was simulated. The obtained results demonstrate that it is necessary to consider also the neutronic feedback effects in the thermal hydraulic calculations to more realistically simulate this type of incident as it is shown in this work.en
dc.format.extent7 pagesen
dc.format.mediumPDFen
dc.identifier.urihttp://hdl.handle.net/2263/61987
dc.language.isoenen
dc.publisherHEFATen
dc.rightsUniversity of Pretoriaen
dc.subjectThermal hydraulicen
dc.subjectTriga IPR-R1 research reactoren
dc.titleThermal hydraulic simulation of the triga ipr-r1 research reactoren
dc.typePresentationen

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