Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA

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@article{97a3a60a087b4e76a3800ea016687425,
title = "Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA",
abstract = "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.",
keywords = "MYRRHA, heavy liquid metal, thermal hydraulics, Lead-cooled fast reactor, experiments",
author = "{Van Tichelen}, Katrien and Graham Kennedy and Fabio Mirelli and Alessandro Marino and Antonio Toti and Davide Rozzia and Edoardo Cascioli and Steven Keijers and Philippe Planquart",
note = "Score=10",
year = "2019",
month = "6",
day = "12",
doi = "10.1080/00295450.2019.1614803",
language = "English",
pages = "1--14",
journal = "Nuclear Technology",
issn = "0029-5450",
publisher = "Springer",

}

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TY - JOUR

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