TY - GEN
T1 - Status and future challenges of liquid metal cooled reactor thermal-hydraulics
AU - Roelofs, Ferry
AU - Van Tichelen, Katrien
AU - Tenchine, Denis
A2 - Schyns, Marc
N1 - Score = 3
PY - 2013/5
Y1 - 2013/5
N2 - Liquid metal cooled reactors are envisaged to play an important role in the future of nuclear energy production because of their possibility to use natural resources efficiently and to reduce the volume and lifetime of nuclear waste. Typically, sodium and lead(-alloys) are envisaged as coolants for such reactors. Obviously, in the development of these reactors, thermal-hydraulics is recognized as a key challenge for design and safety purposes.
This paper will discuss the development status of liquid metal cooled reactor thermal-hydraulics. In addition, the main challenges for future developments will be indicated. Firstly, the technological and safety challenges will be discussed. However, in order address these issues, numerical analysis and associated experimental validation are required. Therefore, emphasis will be put on the important experimental and numerical challenges.
AB - Liquid metal cooled reactors are envisaged to play an important role in the future of nuclear energy production because of their possibility to use natural resources efficiently and to reduce the volume and lifetime of nuclear waste. Typically, sodium and lead(-alloys) are envisaged as coolants for such reactors. Obviously, in the development of these reactors, thermal-hydraulics is recognized as a key challenge for design and safety purposes.
This paper will discuss the development status of liquid metal cooled reactor thermal-hydraulics. In addition, the main challenges for future developments will be indicated. Firstly, the technological and safety challenges will be discussed. However, in order address these issues, numerical analysis and associated experimental validation are required. Therefore, emphasis will be put on the important experimental and numerical challenges.
KW - nuclear
KW - thermal-hydraulics
KW - myrrha
KW - lbe
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_128965
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_128965_2
UR - http://knowledgecentre.sckcen.be/so2/bibref/10247
M3 - In-proceedings paper
T3 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH)
BT - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 15 (NURETH-15)
CY - Pisa, Italy
T2 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 15
Y2 - 12 May 2013 through 17 May 2013
ER -