Thermal hydraulic simulation of the triga ipr-r1 research reactor

Reis, P.A.L.; Costa, A.L.; Pereira, C.; Veloso, M.A.F.; Scari, M.E.; Miro, R.; Verdu, G.

dc.contributor.author	Reis, P.A.L.	en
dc.contributor.author	Costa, A.L.	en
dc.contributor.author	Pereira, C.	en
dc.contributor.author	Veloso, M.A.F.	en
dc.contributor.author	Scari, M.E.	en
dc.contributor.author	Miro, R.	en
dc.contributor.author	Verdu, G.	en
dc.date.accessioned	2017-08-28T07:08:13Z
dc.date.available	2017-08-28T07:08:13Z
dc.date.issued	2016	en
dc.description	Papers 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.abstract	The 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.extent	7 pages	en
dc.format.medium	PDF	en
dc.identifier.uri	http://hdl.handle.net/2263/61987
dc.language.iso	en	en
dc.publisher	HEFAT	en
dc.rights	University of Pretoria	en
dc.subject	Thermal hydraulic	en
dc.subject	Triga IPR-R1 research reactor	en
dc.title	Thermal hydraulic simulation of the triga ipr-r1 research reactor	en
dc.type	Presentation	en