Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box-Reference-Cited by-同舟云学术

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Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box

Published:2022-12-15 Issue:6 Volume:197 Page:1100-1116
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Scuro N. L.¹²^ORCID,Angelo G.³^ORCID,Angelo E.³^ORCID,Piro M. H. A.²^ORCID,Umbehaun P. E.¹^ORCID,Torres W. M.¹^ORCID,Andrade D. A.¹^ORCID

Affiliation:

1. Nuclear and Energy Research Institute, Nuclear Engineering Center, São Paulo, Brazil

2. Ontario Tech University, Department of Energy and Nuclear Engineering, Oshawa, Ontario, Canada

3. Mackenzie Presbyterian University, School of Engineering, São Paulo, Brazil

Funder

Canada Research Chair in Sexual and Gender Minority Health

Comissão Nacional de Energia Nuclear

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2022.2142437

Reference38 articles.

1. Research Reactor Database (RRDB) website, International Atomic Energy Agency; https://nucleus.iaea.org/rrdb/#/home (accessed Jan. 22, 2022).

2. Safety analysis of the IAEA reference research reactor during loss of flow accident using the code MERSAT

3. CFD investigation of flow inversion in typical MTR research reactor undergoing thermal–hydraulic transients

4. Prediction, analysis and solution of flow inversion phenomenon in a typical MTR reactor with upward core cooling

5. Thermal-hydraulic modeling and analysis of a tank in pool reactor for normal operation and loss of flow transient

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