TY - GEN
T1 - Towards Validated Prediction with RANS CFD of Flow and Heat Transport in a Wire-wrap Fuel Assembly
AU - Roelofs, Ferry
AU - Uitslag-Doolaard, Heleen
AU - Dovizio, Daniele
AU - Blaz, Mikuz
AU - Shams, Afaque
AU - Bertocchi, Fulvio
AU - Martin, Rohde
AU - Julio, Pacio
AU - Di Piazza, Ivan
AU - Kennedy, Graham
AU - Van Tichelen, Katrien
AU - Obabko, Alex
AU - Merzari, Elia
N1 - Score=3
PY - 2019/3/19
Y1 - 2019/3/19
N2 - Liquid metal fast reactors (LMFRs) are foreseen to play an important role in the future of nuclear energy, thanks to their increased fuel utilization and safety features profiting from the optimal heat transfer performance of the metallic coolants. Accurate thermal-hydraulic analysis of their fuel assemblies, typically employed with wire-wraps as spacers, is recognized as a crucial scientific and engineering contribution in order to support the deployment of such technology. This challenges the modeling and simulation community.
To this aspect, various reference databases (both experimental and numerical) for different wire-wrapped fuel assembly configurations have been created recently and are being used for validation of engineering simulation approaches based on Reynolds Averaged Navier Stokes (RANS) modelling. These databases include:
7-pin rod bundle: A detailed experiment with Particle Image Velocimetry (PIV) is performed for a Reynolds number of 21600. In order to allow accurate measurements of the flow topology, a matched-index-of-refraction technique was used employing water as working fluid.
19-pin bundle: A series of experiments is performed covering a wide range of Reynolds and Peclet numbers as well as thermal powers. The experiments use liquid lead-bismuth eutectic as working fluid. The measurements include pressure drop and local temperatures.
61-pin rod bundle: This large eddy simulation including conjugate heat transfer from the pin cladding to the coolant allows to bridge the gap from small bundles (less than 37 pins) to large bundles (more than 37 pins). In literature, a fundamental different behavior has been observed for small bundles compared to large bundles.
127-pin bundle: Isothermal experiments using lead-bismuth eutectic characterizing pressure drop are performed on a full scale fuel assembly representative for the MYRRHA reactor.
Infinite pin bundle: This reference quasi-direct numerical simulation profits from periodicity in all directions. It provides a detailed view into the flow field and in addition reveals details of the heat transfer from the rod bundle into the flow.
Reference databases aim to serve the nuclear scientific community to validate engineering simulation approaches. The paper will introduce these reference databases, and how they have been used to validate RANS based turbulence modelling approaches.
AB - Liquid metal fast reactors (LMFRs) are foreseen to play an important role in the future of nuclear energy, thanks to their increased fuel utilization and safety features profiting from the optimal heat transfer performance of the metallic coolants. Accurate thermal-hydraulic analysis of their fuel assemblies, typically employed with wire-wraps as spacers, is recognized as a crucial scientific and engineering contribution in order to support the deployment of such technology. This challenges the modeling and simulation community.
To this aspect, various reference databases (both experimental and numerical) for different wire-wrapped fuel assembly configurations have been created recently and are being used for validation of engineering simulation approaches based on Reynolds Averaged Navier Stokes (RANS) modelling. These databases include:
7-pin rod bundle: A detailed experiment with Particle Image Velocimetry (PIV) is performed for a Reynolds number of 21600. In order to allow accurate measurements of the flow topology, a matched-index-of-refraction technique was used employing water as working fluid.
19-pin bundle: A series of experiments is performed covering a wide range of Reynolds and Peclet numbers as well as thermal powers. The experiments use liquid lead-bismuth eutectic as working fluid. The measurements include pressure drop and local temperatures.
61-pin rod bundle: This large eddy simulation including conjugate heat transfer from the pin cladding to the coolant allows to bridge the gap from small bundles (less than 37 pins) to large bundles (more than 37 pins). In literature, a fundamental different behavior has been observed for small bundles compared to large bundles.
127-pin bundle: Isothermal experiments using lead-bismuth eutectic characterizing pressure drop are performed on a full scale fuel assembly representative for the MYRRHA reactor.
Infinite pin bundle: This reference quasi-direct numerical simulation profits from periodicity in all directions. It provides a detailed view into the flow field and in addition reveals details of the heat transfer from the rod bundle into the flow.
Reference databases aim to serve the nuclear scientific community to validate engineering simulation approaches. The paper will introduce these reference databases, and how they have been used to validate RANS based turbulence modelling approaches.
KW - fuel assembly
KW - myrrha
KW - liquid metal
KW - thermal hydraulics
KW - Wire wrapped fuel assembly
KW - experiments
KW - CFD
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/35084860
UR - http://sesame-h2020.eu/wp-content/uploads/2015/08/SESAME-Workshop-Program-Final.pdf
M3 - In-proceedings paper
SP - 1
EP - 11
BT - SESAME international workshop
PB - Unknown
T2 - SESAME International Workshop
Y2 - 19 March 2019 through 21 March 2019
ER -