Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA
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Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA. / Van Tichelen, Katrien; Kennedy, Graham; Mirelli, Fabio; Marino, Alessandro; Toti, Antonio; Rozzia, Davide; Cascioli, Edoardo; Keijers, Steven; Planquart, Philippe.
In: Nuclear Technology, 12.06.2019, p. 1-14.Research output: Contribution to journal › Literature review
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T1 - Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA
AU - Van Tichelen, Katrien
AU - Kennedy, Graham
AU - Mirelli, Fabio
AU - Marino, Alessandro
AU - Toti, Antonio
AU - Rozzia, Davide
AU - Cascioli, Edoardo
AU - Keijers, Steven
AU - Planquart, Philippe
N1 - Score=10
PY - 2019/6/12
Y1 - 2019/6/12
N2 - The Belgian Nuclear Research Centre (SCK•CEN) is at the forefront of heavy liquid-metal (HLM) nuclear technology worldwide with the development of the Multi-purpose hYbrid Research Reactor for High-tech Applications (MYRRHA) accelerator-driven system. MYRRHA is a flexible fast-spectrum pool-type research reactor cooled by lead bismuth eutectic (LBE) and has been identified as the European Technology Pilot Plant for the lead-cooled fast reactor. Given the innovative nature of MYRRHA, the project is currently going through a prelicensing phase. The MYRRHA research and development (R&D) program is driven by this prelicensing process and aims to fill the existing gaps in knowledge with respect to LBE chemistry, material behavior, fuel behavior, instrumentation, and HLM thermal hydraulics. In this paper we present selected topics from the R&D program on HLM thermal hydraulics that are essential for the design, engineering, and safety analysis of MYRRHA and other HLM-cooled reactors. The topics addressed include turbulent heat transfer in HLM, fuel assembly thermal hydraulics and flow-induced vibrations, control rod hydrodynamics, primary heat exchanger pool and integral system thermal hydraulics, sloshing, and multiphysics modeling.
AB - The Belgian Nuclear Research Centre (SCK•CEN) is at the forefront of heavy liquid-metal (HLM) nuclear technology worldwide with the development of the Multi-purpose hYbrid Research Reactor for High-tech Applications (MYRRHA) accelerator-driven system. MYRRHA is a flexible fast-spectrum pool-type research reactor cooled by lead bismuth eutectic (LBE) and has been identified as the European Technology Pilot Plant for the lead-cooled fast reactor. Given the innovative nature of MYRRHA, the project is currently going through a prelicensing phase. The MYRRHA research and development (R&D) program is driven by this prelicensing process and aims to fill the existing gaps in knowledge with respect to LBE chemistry, material behavior, fuel behavior, instrumentation, and HLM thermal hydraulics. In this paper we present selected topics from the R&D program on HLM thermal hydraulics that are essential for the design, engineering, and safety analysis of MYRRHA and other HLM-cooled reactors. The topics addressed include turbulent heat transfer in HLM, fuel assembly thermal hydraulics and flow-induced vibrations, control rod hydrodynamics, primary heat exchanger pool and integral system thermal hydraulics, sloshing, and multiphysics modeling.
KW - MYRRHA
KW - heavy liquid metal
KW - thermal hydraulics
KW - Lead-cooled fast reactor
KW - experiments
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/34950099
U2 - 10.1080/00295450.2019.1614803
DO - 10.1080/00295450.2019.1614803
M3 - Literature review
SP - 1
EP - 14
JO - Nuclear Technology
JF - Nuclear Technology
SN - 0029-5450
ER -
ID: 5468817