skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Experimental Study on the Effect of Localized Blockages on the Friction Factor of a 61-Pin Wire-Wrapped Bundle

Journal Article · · Journal of Fluids Engineering
DOI:https://doi.org/10.1115/1.4048140· OSTI ID:1850519
 [1];  [2];  [1];  [1];  [3]
  1. Department of Nuclear Engineering, Texas A&M University, College Station, TX 77845
  2. Department of Mechanical Engineering, Texas A&M University, College Station, TX 77845
  3. Department of Nuclear Engineering, Department of Mechanical Engineering, Texas A&M University, College Station, TX 77845

Abstract The thermal-hydraulic behavior of the flow in rod bundles has motivated numerous experimental and computational investigations. Previous studies have identified potential for accumulation of debris within the small subchannels of typical wire-wrapped assemblies with subsequent total or partial blockage of subchannel coolant flow. A test campaign was conducted to study the effects of localized blockages on the bundle averaged friction factor of a tightly packed wire-wrapped rod bundle. Blockages were installed within the bundle, and fluid pressure drop was measured across one wire pitch for a Reynolds number range of 500–17,200. The Darcy–Weisbach friction factor of the perturbed rod bundle geometry was compared with that of the unblocked bundle, as well as with the predictions of a well-established friction factor correlation. Differing effects based on blockage size and location for various flow regimes were studied. A number of conclusions can be made about the effects of the blockages on the friction factor, such as an increasing effect of the blockage on friction factor with an increase in Reynolds number, a change in flow behavior in the turbulent transition flow regime near Reynolds number 3000, differences in effect on friction factor for different types of subchannel blockage, and a nonlinear trend in friction factor variation with flow area impeded for edge subchannels. To this end, all data and quantified uncertainty produced in this study are made available for comparison and validation of advanced computational tools.

Research Organization:
Texas A & M Univ., College Station, TX (United States). Texas A & M Engineering Experiment Station
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
NE0008652
OSTI ID:
1850519
Journal Information:
Journal of Fluids Engineering, Vol. 142, Issue 11; ISSN 0098-2202
Publisher:
ASME
Country of Publication:
United States
Language:
English

References (34)

Turbulent transport in wall subchannels and in finite rod clusters journal June 1991
Fluid flow investigations within a 37 element CANDU fuel bundle supported by magnetic resonance velocimetry and computational fluid dynamics journal August 2017
URANS prediction of flow fluctuations in rod bundle with split-type spacer grid journal April 2017
Numerical prediction of flow and heat transfer in a loosely spaced bare rod bundle journal October 2018
Pressure drop performance of rod bundles in hexagonal arrangements journal December 1972
Pressure Drop Correlations for Fuel Element Spacers journal January 1973
Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parameters journal April 1986
Numerical implementation of the Cheng and Todreas correlation for wire wrapped bundle friction factors-desirable improvements in the transition flow region journal October 2013
Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles journal February 2014
Experimental investigation on the influence of gap vortex streets on fluid-structure interactions in hexagonal bundle geometries journal October 2019
Understanding migratory flow caused by helicoid wire spacers in rod bundles: An experimental and theoretical study journal December 2019
Mean Pressure Distribution and Drag Coefficient of Wire-Wrapped Cylinders journal June 1994
An experimental study and assessment of existing friction factor correlations for wire-wrapped fuel assemblies journal November 2001
Measurement of Pressure Drop in a Full-Scale Fuel Assembly of a Liquid Metal Reactor journal May 2003
Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor journal April 2016
Experimental Study of the Diversion Crossflow Caused by Subchannel Blockages. Part I: Experimental Procedures and Mass Flow Rates in the Channels journal December 1984
Experimental Study of the Diversion Crossflow Caused by Subchannel Blockages. Part II: Pressures in the Channels and the Comparison of the COBRA III-C Predictions With Experimental Data journal December 1984
Blocked Flow Subchannel Simulation Comparison With Single-Phase Flow Data journal June 1992
Simulating fuel assemblies with low resolution CFD approaches journal September 2012
A CFD analysis of flow blockage phenomena in ALFRED LFR demo fuel assembly journal September 2014
Thermal hydraulic investigations on porous blockage in a prototype sodium cooled fast reactor fuel pin bundle journal July 2016
Turbulent flow and vortex characteristics in a blocked subchannel of a helically wrapped rod bundle journal July 2019
High-fidelity velocity measurements in a totally blocked interior subchannel of a wire-wrapped 61-pin hexagonal fuel bundle journal November 2019
CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle journal April 2019
Blockage fuel pin simulator experiments and simulation journal November 2019
Numerical investigation of flow blockage accident in SFR fuel assembly journal April 2020
Analysis of flow and heat transfer through a partially blocked fuel subassembly of fast breeder reactor journal January 2020
Turbulent Transverse Plane PIV Measurements on a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle
  • Goth, Nolan E.; Jones, Philip; Nguyen, Thien D.
  • 2018 26th International Conference on Nuclear Engineering, Volume 6A: Thermal-Hydraulics and Safety Analyses https://doi.org/10.1115/ICONE26-81462
conference October 2018
PIV measurements of turbulent flows in a 61-pin wire-wrapped hexagonal fuel bundle journal June 2017
Stereoscopic PIV measurements of near-wall flow in a tightly packed rod bundle with wire spacers journal April 2018
PTV/PIV measurements of turbulent flows in interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle journal June 2018
The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles journal August 2018
The Tait equation: 100 years on journal November 1988
An investigation of matched index of refraction technique and its application in optical measurements of fluid flow journal November 2012

Similar Records

Experimental investigation of turbulent wake flows in a helically wrapped rod bundle in presence of localized blockages
Journal Article · Wed Jul 01 00:00:00 EDT 2020 · Physics of Fluids · OSTI ID:1850519

Turbulent flow and vortex characteristics in a blocked subchannel of a helically wrapped rod bundle
Journal Article · Tue Jul 23 00:00:00 EDT 2019 · Experiments in Fluids · OSTI ID:1850519

Particle Image Velocimetry Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle
Journal Article · Fri Jul 01 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1850519

Related Subjects