Modeling of the fluid flow and heat transfer in a pebble bed modular reactor core with a computational fluid dynamics code

International Conference on Nuclear Engineering, Proceedings, ICONE

Volumn 2, Issue , 2002, Pages 649-658

  Taylor, J Bryce ^a   Yavuzkurt, Savas ^a   Baratta, Anthony J ^a  

^a PENNSYLVANIA STATE UNIVERSITY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

PEEBLE BED MODULAR REACTOR CORE; SOFTWARE PACKAGE FLUENT;

COMPUTATIONAL FLUID DYNAMICS; COMPUTER AIDED ANALYSIS; HEAT TRANSFER; LAMINAR FLOW; NUCLEAR REACTOR SIMULATORS; NUSSELT NUMBER; PRESSURE DROP; PRESSURE MEASUREMENT; REACTOR CORES; TEMPERATURE MEASUREMENT; TURBULENT FLOW; VELOCITY MEASUREMENT;

GAS COOLED REACTORS;

EID: 0036388136     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/ICONE10-22286     Document Type: Conference Paper

References (14)

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4. Storey, Greg, Exelon Generation. private communication.
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14. Baratta, A.J., Yavuzkurt, S, and Miller, T. "A Numerical and Experimental Investigation of the Coolant Flow, Fuel and Fluid Heat Transfer, and Fuel Thermal Stress in a Gas-Cooled Pebble Bed Reactor." Research Proposal for the Nuclear Engineering Education Research Program, submitted November 1, 2001.