TY - GEN
T1 - LARGE EDDY SIMULATION OF HEAT TRANSFER IN A 7 PIN WIRE-WRAPPED ROD BUNDLE
AU - Dutra, Carolina S.B.
AU - Merzari, Elia
N1 - Publisher Copyright:
© 2022 ATH. All Rights Reserved.
PY - 2022
Y1 - 2022
N2 - The core of Sodium Fast Reactor (SFR) is formed by multiple hydraulically isolated assemblies. Within each assembly, there is a tightly packed triangular lattice array of fuel pins enclosed in a hexagonal duct. Helical wire spacers are wrapped along the axis of the rods to maintain a gap between them, inducing the secondary flow, increasing the channel mixing, and enhancing the convective heat transfer. This work presents Large Eddy Simulations for a simplified 7-pin wire-wrapper geometry with heat transfer in low-flow conditions. We focus on three cases, with Reynolds number of Re = 1000, 5000, and 10000 and the Prandtl number of Pr = 0.005. Also, a mesh resolution study is performed to produce a mesh suitable for a future Direct Numerical Simulation campaign. Finally, we discussed the results and compared the heat transfer predictions between our numerical results and classic correlations.
AB - The core of Sodium Fast Reactor (SFR) is formed by multiple hydraulically isolated assemblies. Within each assembly, there is a tightly packed triangular lattice array of fuel pins enclosed in a hexagonal duct. Helical wire spacers are wrapped along the axis of the rods to maintain a gap between them, inducing the secondary flow, increasing the channel mixing, and enhancing the convective heat transfer. This work presents Large Eddy Simulations for a simplified 7-pin wire-wrapper geometry with heat transfer in low-flow conditions. We focus on three cases, with Reynolds number of Re = 1000, 5000, and 10000 and the Prandtl number of Pr = 0.005. Also, a mesh resolution study is performed to produce a mesh suitable for a future Direct Numerical Simulation campaign. Finally, we discussed the results and compared the heat transfer predictions between our numerical results and classic correlations.
UR - https://www.scopus.com/pages/publications/85202858484
UR - https://www.scopus.com/inward/citedby.url?scp=85202858484&partnerID=8YFLogxK
U2 - 10.13182/T126-38433
DO - 10.13182/T126-38433
M3 - Conference contribution
AN - SCOPUS:85202858484
T3 - Proceedings of Advances in Thermal Hydraulics, ATH 2022 - Embedded with the 2022 ANS Annual Meeting
SP - 417
EP - 429
BT - Proceedings of Advances in Thermal Hydraulics, ATH 2022 - Embedded with the 2022 ANS Annual Meeting
PB - American Nuclear Society
T2 - 5th International Topical Meeting on Advances in Thermal Hydraulics 2022, ATH 2022, held in conjunction with the 2022 American Nuclear Society ,ANS Annual Meeting
Y2 - 12 June 2022 through 16 June 2022
ER -