Computational fluid dynamics modeling of two-phase flow in a BWR fuel assembly. Final CRADA Report.
A direct numerical simulation capability for two-phase flows with heat transfer in complex geometries can considerably reduce the hardware development cycle, facilitate the optimization and reduce the costs of testing of various industrial facilities, such as nuclear power plants, steam generators, steam condensers, liquid cooling systems, heat exchangers, distillers, and boilers. Specifically, the phenomena occurring in a two-phase coolant flow in a BWR (Boiling Water Reactor) fuel assembly include coolant phase changes and multiple flow regimes which directly influence the coolant interaction with fuel assembly and, ultimately, the reactor performance. Traditionally, the best analysis tools for this purpose of two-phase flow phenomena inside the BWR fuel assembly have been the sub-channel codes. However, the resolution of these codes is too coarse for analyzing the detailed intra-assembly flow patterns, such as flow around a spacer element. Advanced CFD (Computational Fluid Dynamics) codes provide a potential for detailed 3D simulations of coolant flow inside a fuel assembly, including flow around a spacer element using more fundamental physical models of flow regimes and phase interactions than sub-channel codes. Such models can extend the code applicability to a wider range of situations, which is highly important for increasing the efficiency and to prevent accidents.
- Research Organization:
- Argonne National Laboratory (ANL)
- Sponsoring Organization:
- NNSA
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 967950
- Report Number(s):
- ANL/NE-C0202101
- Country of Publication:
- United States
- Language:
- ENGLISH
Similar Records
Advances in Computational Fluid Dynamics Modeling of Two Phase Flow in a Boiling Water Reactor Fuel Assembly
Experimental Study of Two Phase Flow Behavior Past BWR Spacer Grids
Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis.
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:20995456
Experimental Study of Two Phase Flow Behavior Past BWR Spacer Grids
Conference
·
Mon Jul 01 00:00:00 EDT 2002
·
OSTI ID:21072849
Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis.
Conference
·
Sun Dec 31 23:00:00 EST 2006
·
OSTI ID:944030