Published December 15, 2016 | Version v1
Journal article

Prediction of interfacial area transport in a scaled 8×8 BWR rod bundle

  • 1. School of Nuclear Engineering, Purdue University, 400 Central Dr., West Lafayette, IN 47907-2017 (United States)
  • 2. U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 (United States)

Description

In the two-fluid model, it is important to give an accurate prediction for the interfacial area concentration. In order to achieve this goal, the interfacial area transport equation has been developed. This study focuses on the benchmark of IATE performance in a rod bundle geometry. A set of interfacial area concentration source and sink term models are proposed for a rod bundle geometry based on the confined channel IATE model. This model was selected as a basis because of the relative similarity of the two geometries. Benchmarking of the new model with interfacial area concentration data in an 8×8 rod bundle test section which has been scaled from an actual BWR fuel bundle is performed. The model shows good agreement in bubbly and cap-bubbly flows, which are similar in many types of geometries, while it shows some discrepancy in churn-turbulent flow regime. This discrepancy may be due to the geometrical differences between the actual rod bundle test facility and the facility used to collect the data which benchmarked the original source and sink models.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2016.10.037

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2016.10.037;
PII
S0029-5493(16)30414-9;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
310
Journal Page Range
p. 638-647
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.