TY - GEN
T1 - Development and validation of a computational fluid dynamics model for the simulation of two-phase flow phenomena in a boiling water reactor fuel assembly
AU - Tentner, Adrian
AU - Pointer, W. David
AU - Lo, Simon
AU - Splawski, Andrew
PY - 2009
Y1 - 2009
N2 - This paper presents the current status in the development and validation of an advanced Computational Fluid Dynamics (CFD) model, CFD-BWR, which allows the detailed analysis of the two-phase flow and heat transfer phenomena in Boiling Water Reactor (BWR) fuel assemblies under various operating conditions. The CFD-BWR model uses an Eulerian Two-Phase (E2P) approach, and is also referred to as the E2P modeling framework. It is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities. The integral validation efforts have focused on the analysis of the NUPEC Full-Size Boiling Water Reactor Test (BFBT) within the framework of the OECD/NRC benchmark exercise. The paper reviews the two-phase models implemented in the CFD-BWR code, and emphasizes recently implemented models of inter-phase and coolant-cladding momentum and energy exchanges. Results of recent BFBT experiment simulations using these models are presented and the effects of the new models on the calculated void distribution are discussed. The paper concludes with a discussion of future model development and validation plans.
AB - This paper presents the current status in the development and validation of an advanced Computational Fluid Dynamics (CFD) model, CFD-BWR, which allows the detailed analysis of the two-phase flow and heat transfer phenomena in Boiling Water Reactor (BWR) fuel assemblies under various operating conditions. The CFD-BWR model uses an Eulerian Two-Phase (E2P) approach, and is also referred to as the E2P modeling framework. It is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities. The integral validation efforts have focused on the analysis of the NUPEC Full-Size Boiling Water Reactor Test (BFBT) within the framework of the OECD/NRC benchmark exercise. The paper reviews the two-phase models implemented in the CFD-BWR code, and emphasizes recently implemented models of inter-phase and coolant-cladding momentum and energy exchanges. Results of recent BFBT experiment simulations using these models are presented and the effects of the new models on the calculated void distribution are discussed. The paper concludes with a discussion of future model development and validation plans.
UR - http://www.scopus.com/inward/record.url?scp=77952904543&partnerID=8YFLogxK
U2 - 10.1115/ICONE17-75135
DO - 10.1115/ICONE17-75135
M3 - Conference contribution
AN - SCOPUS:77952904543
SN - 9780791843550
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
SP - 275
EP - 284
BT - Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17
T2 - 17th International Conference on Nuclear Engineering, ICONE17
Y2 - 12 July 2009 through 16 July 2009
ER -