Investigation of natural convection heat transfer in a unique scaled-down dual-channel facility-Reference-Cited by-同舟云学术

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Investigation of natural convection heat transfer in a unique scaled-down dual-channel facility

Published:2016-11-28 Issue:1 Volume:63 Page:387-396
ISSN:0001-1541
Container-title:AIChE Journal
language:en
Short-container-title:AIChE J.

Author:

Said Ibrahim A.¹,Taha Mahmoud M.¹,Usman Shoaib²,Woods Brian G.³,Al-Dahhan Muthanna H.¹²

Affiliation:

1. Chemical and Biochemical Engineering Dept.; Missouri University of Science and Technology; Rolla MO 65409

2. Mining and Nuclear Engineering Dept.; Missouri University of Science and Technology; Rolla MO 65409-0170

3. Dept. of Nuclear Engineering and Radiation Health Physics; Oregon State University; Corvallis OR 97331

Funder

U.S. Department of Energy-Nuclear Energy Research Initiative (DOE-NERI)

Publisher

Wiley

Subject

General Chemical Engineering,Environmental Engineering,Biotechnology

Reference22 articles.

1. CFD analysis and assessment for cross-flow phenomena in VHTR prismatic core;Lee;Heat Transf Eng.,2014

2. Study of natural circulation in a VHTR after a LOFA using different turbulence models;Tung;Nucl Eng Des.,2013

3. Thermal-hydraulics analyses for 1/6 prismatic VHTR core and fuel element with and without bypass flow;Travis;Energy Convers Manag.,2013

4. Modeling strategies to compute natural circulation using CFD in a VHTR after a LOFA;Tung;Nucl Eng Des.,2014

5. Thermal response of a modular high temperature reactor during passive cooldown under pressurized and depressurized conditions;Haque;Nucl Eng Des.,2006

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1. Investigation of Natural Helium Circulation Inside Dual Channels Prismatic Modular Reactor;Annals of Nuclear Energy;2024-11

2. Investigation of computational model for the natural circulation at dual channel facility;Nuclear Engineering and Technology;2024-08

3. Characterizing passive flow in nuclear prismatic modular reactor core channels: Temperature, velocity, and heat transfer analysis;Applied Thermal Engineering;2024-03

4. Effect of non-uniform heating on temperature and velocity profiles of buoyancy driven flow in vertical channel of prismatic modular reactor core;Applied Thermal Engineering;2023-05

5. Benchmark Validation Experiment of Plenum-to-Plenum Flow Through Heated Parallel Channels;Journal of Verification, Validation and Uncertainty Quantification;2021-11-09

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