CFD analysis of localized crud effects on the flow of coolant in nuclear rod bundles-Reference-Cited by-同舟云学术

CFD analysis of localized crud effects on the flow of coolant in nuclear rod bundles

Published:2016-08 Issue: Volume:305 Page:28-38
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Cinosi N.^ORCID,Walker S.P.

Funder

EPSRC

CD-adapco

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference23 articles.

1. CFD Modeling of Fuel Rod Heat Transfer to Aid in the Risk Assessment of Fuel ROD Failure Due to Localized Crud;Beltz,2009

2. Halden in-reactor test to exhibit PWR axial offset anomaly;Bennett;EPRI,2004

3. Can corrosion and CRUD actually improve safety margins in LWRs?;Buongiorno;Ann. Nucl. Energy,2014

4. Pressurized Water Reactor Core Crud Mapping;Byers,2010

5. Momentum Transfer in Boundary Layers;Cebeci,1977

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2. Investigation on turbulent heat transfer to lead-bismuth eutectic flows in rough rod bundles for nuclear applications;International Journal of Thermal Sciences;2024-10

3. Development of Nusselt number and friction factor models for rough rod bundles based on wall functions;Annals of Nuclear Energy;2024-04

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