FloEFD Calculation Assessment to Experimental Data in Nuclear Safety Case-Reference-Cited by-同舟云学术

FloEFD Calculation Assessment to Experimental Data in Nuclear Safety Case

Published:2014-07-07 Issue: Volume: Page:
ISSN:
Container-title:Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory
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Author:

Philipov Svetlin¹,Popov Dimitar²,Batakliev Krasimir³

Affiliation:

1. Risk Engineering Ltd., Sofia, Bulgaria

2. Kozloduy NPP, Bulgaria

3. HayCAD Infotech, Plovdiv, Bulgaria

Abstract

This paper presents the results of comparison between CFD code FloEFD and an experiment in Kozloduy NPP concerning coolant mixing. This comparison is done with purpose to find out behavior of FloEFD to manage complex tasks. Real experimental data is used from a performed experiment in the frame of an international project on nuclear safety. The main assessment point is the temperature distribution of the coolant at core inlet. A representative parameter is considered axis of minimal mixing. Also, temperature distribution in the down chamber at level 2.5m from the bottom is assessed.

Publisher

American Society of Mechanical Engineers

Link

http://asmedigitalcollection.asme.org/ICONE/proceedings-pdf/doi/10.1115/ICONE22-30411/4249510/v004t10a014-icone22-30411.pdf

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