Fluid flow in a diametrally expanded CANDU fuel channel – Part 2: Computational study-Reference-Cited by-同舟云学术

Fluid flow in a diametrally expanded CANDU fuel channel – Part 2: Computational study

Published:2020-02 Issue: Volume:357 Page:110372
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Piro M.H.A.,Christon M.,Tensuda B.,Poschmann M.,Bruschewski M.,Grundmann S.,Tropea C.

Funder

Canada Research Chairs

Natural Sciences and Engineering Research Council of Canada

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

Reference24 articles.

1. Experimental and Numerical Investigations of Three-Dimensional Turbulent Flow of Water Surrounding a CANDU Simulation Fuel Bundle Structure Inside a Channel;Abbasian;Nucl. Eng. Des.,2009

2. Numerical Simulation of Turbulent Flow Through a 37 Element CANDU Fuel Bundle;Bhattacharya;Ann. Nucl. Energy,2012

3. New Insights Into The Flow Inside CANDU Fuel Bundles Using Magnetic Resonance Velocimetry;Bruschewski,2016

4. Fluid flow in a diametrally crept CANDU fuel channel – part 1: experimental study;Bruschewski;Nucl. Eng. Des.,2019

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1. Computational fluid dynamic investigations of flow bypass through an aged CANDU pressure tube;Annals of Nuclear Energy;2022-12

2. Mesh and turbulence model sensitivity analyses of computational fluid dynamic simulations of a 37M CANDU fuel bundle;Nuclear Engineering and Technology;2022-11

3. Multilevel modeling of diametral creep in pressure tubes of Korean CANDU units;Nuclear Engineering and Technology;2021-12

4. Commissioning of an MRI test facility for CFD-grade flow experiments in replicas of nuclear fuel assemblies and other reactor components;Nuclear Engineering and Design;2021-04

5. Review of sub-channel code development for pressurized water reactor and introduction of CORTH-V2.0 sub-channel code;Progress in Nuclear Energy;2020-07