A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors

Journal Article · Thu Sep 08 00:00:00 EDT 2016 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2016.08.018· OSTI ID:1339576

Hu, Rui ^[1]; Yu, Yiqi ^[1]

---

1. Argonne National Lab. (ANL), Argonne, IL (United States)

For efficient and accurate temperature predictions of sodium fast reactor structures, a 3-D full-core conjugate heat transfer modeling capability is developed for an advanced system analysis tool, SAM. The hexagon lattice core is modeled with 1-D parallel channels representing the subassembly flow, and 2-D duct walls and inter-assembly gaps. The six sides of the hexagon duct wall and near-wall coolant region are modeled separately to account for different temperatures and heat transfer between coolant flow and each side of the duct wall. The Jacobian Free Newton Krylov (JFNK) solution method is applied to solve the fluid and solid field simultaneously in a fully coupled fashion. The 3-D full-core conjugate heat transfer modeling capability in SAM has been demonstrated by a verification test problem with 7 fuel assemblies in a hexagon lattice layout. In addition, the SAM simulation results are compared with RANS-based CFD simulations. Very good agreements have been achieved between the results of the two approaches.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE). Nuclear Energy Advanced Modeling and Simulation (NEAMS)
• Grant/Contract Number: AC02-06CH11357
• OSTI ID: 1339576
• Alternate ID(s): OSTI ID: 1397894
• Journal Information: Nuclear Engineering and Design, Vol. 308, Issue C; ISSN 0029-5493
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
JFNK
conjugate heat transfer
sodium fast reactor
system thermal-hydraulics