Influence of the 3-D Phenomena on the Safety Parameters during a ULOF Accident in the MYRRHA Reactor

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Abstract

In a pool type liquid metal cooled reactor like MYRRHA, the influence of 3-D thermal-hydraulic phenomena during Loss Of Flow (LOF) transients can potentially have an important impact on safety-relevant parameters. 3-D temperature distributions and local pressure gradients may affect the evolution of the coolant mass flow during the transition from forced to natural convection, with the possible generation of flow instabilities and dissipating flows. Furthermore, the presence of stagnant volumes may influence the characteristic propagation time of perturbations through the system. The 1-D computational system codes used to perform reactor safety analyses were originally developed for loop type reactor designs that foresee the coolant flowing in pipes, with energy losses mainly due to wall friction. Therefore, this class of codes is not validated to simulate correctly the physics of the phenomena occurring in a pool type reactor. The objective of this work is to assess the shortcomings of 1-D system codes in predicting the response of the MYRRHA reactor to a LOF event, identifying the 3-D safety-relevant phenomena that can have an influence on the transient evolution. The adopted strategy is comparing the transient simulation results of the RELAP5 thermal-hydraulic system code with reference CFD simulations.

Details

Original languageEnglish
Title of host publication16th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16)
Place of PublicationUnited States
Pages4703-4716
ISBN (Electronic)978-0-89448-722-4
Publication statusPublished - Aug 2015
EventNURETH 2015- 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics - American Nuclear Society, Chicago, United States
Duration: 30 Aug 20154 Sep 2015

Publication series

NameNURETH - International Topical Meeting on Nuclear Reactor Thermalhydraulics
Number16

Conference

ConferenceNURETH 2015- 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics
CountryUnited States
CityChicago
Period2015-08-302015-09-04

Keywords

  • MYRRHA, Loss of flow, CFD, system code, 3-D phenomena

ID: 219338