Abstract
MYRRHA is a multi-purpose hybrid pool-type research reactor cooled with lead-bismuth eutectic (LBE)
that is under design at the Belgian nuclear research center SCK•CEN. The European Scaled Pool
Experiment (E-SCAPE) is a thermal hydraulic 1/6th-scale model of the MYRRHA reactor developed
within the European framework programs THINS and MYRTE.
The experiments from the E-SCAPE facility are essential for the design and licensing of MYRRHA. First
of all, these experiments can provide information on the flow patterns and heat transport in the different
compartments of the reactor. Secondly, the data from the E-SCAPE experiments can be used for
qualification of thermal hydraulic computer codes that will be applied for analyzing the flow and heat
transport in the MYRRHA reactor. Considering the rare and typical conditions in heavy liquid cooled
nuclear reactors, thorough validation of these codes against relevant experimental data is a prerequisite
before application.
This paper presents the approach followed by NRG to model the flow and heat transport in E-SCAPE
using the Computational Fluid Dynamics (CFD) code STAR-CCM+. CFD analyses for different forced
flow conditions are presented and compared with experimental results. The predicted temperature
distribution in the pool, core and plena agrees well with the temperature measurements from E-SCAPE.
Original language | English |
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Title of host publication | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18 |
Publisher | American Nuclear Society |
Pages | 1-11 |
Number of pages | 11 |
State | Published - 18 Aug 2019 |
Event | 2019 - NURETH: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics - Portland Marriott Downtown Waterfront, Portland Duration: 18 Aug 2019 → 23 Aug 2019 http://epsr.ans.org/meeting/?m=285 |
Conference
Conference | 2019 - NURETH |
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Abbreviated title | NURETH18 |
Country/Territory | United States |
City | Portland |
Period | 2019-08-18 → 2019-08-23 |
Internet address |