Natural convection inside heated channel of a facility representing prismatic modular reactor core
Published 2018 View Full Article
- Home
- Publications
- Publication Search
- Publication Details
Title
Natural convection inside heated channel of a facility representing prismatic modular reactor core
Authors
Keywords
-
Journal
AICHE JOURNAL
Volume -, Issue -, Pages -
Publisher
Wiley
Online
2018-04-19
DOI
10.1002/aic.16185
References
Ask authors/readers for more resources
Related references
Note: Only part of the references are listed.- Buoyancy-driven air flow within plenum-to-plenum facility down-comer channel
- (2018) Mahmoud M. Taha et al. EXPERIMENTAL THERMAL AND FLUID SCIENCE
- Experimental investigation of the helium natural circulation heat transfer in two channels facility using varying riser channel heat fluxes
- (2018) Ibrahim A. Said et al. EXPERIMENTAL THERMAL AND FLUID SCIENCE
- Effect of helium pressure on natural convection heat transfer in a prismatic dual-channel circulation loop
- (2018) Ibrahim A. Said et al. INTERNATIONAL JOURNAL OF THERMAL SCIENCES
- Natural convection heat transfer inside an open vertical pipe: Influences of length, diameter and Prandtl number
- (2017) Seung-Min Ohk et al. INTERNATIONAL JOURNAL OF THERMAL SCIENCES
- Experimental and Computational Assessment of Core Bypass Flow in Block-Type Very High Temperature Reactor
- (2017) Su-Jong Yoon et al. NUCLEAR TECHNOLOGY
- Investigation of natural convection heat transfer in a unique scaled-down dual-channel facility
- (2016) Ibrahim A. Said et al. AICHE JOURNAL
- Flow downward penetration of vertical parallel plates natural convection with an asymmetrically heated wall
- (2016) Wu-Shung Fu et al. INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER
- Numerical and experimental investigation of unsteady natural convection in a non-uniformly heated vertical open-ended channel
- (2016) O.A. Tkachenko et al. INTERNATIONAL JOURNAL OF THERMAL SCIENCES
- Preliminary tests of particle image velocimetry for the upper plenum of a scaled model of a very high temperature gas cooled reactor
- (2015) Kyle L. McVay et al. PROGRESS IN NUCLEAR ENERGY
- A review of modern advances in analyses and applications of single-phase natural circulation loop in nuclear thermal hydraulics
- (2014) Dipankar N. Basu et al. NUCLEAR ENGINEERING AND DESIGN
- Thermal–hydraulics analyses for 1/6 prismatic VHTR core and fuel element with and without bypass flow
- (2013) Boyce W. Travis et al. ENERGY CONVERSION AND MANAGEMENT
- Numerical study on thermal stratification phenomena in upper plenum of LMFBR “MONJU”
- (2013) Makoto Shibahara et al. NUCLEAR ENGINEERING AND DESIGN
- Experimental investigation of turbulent natural convection in a vertical water channel with symmetric heating: Flow and heat transfer
- (2012) C. Daverat et al. EXPERIMENTAL THERMAL AND FLUID SCIENCE
- Transitional natural convection flow and heat transfer in an open channel
- (2012) E. Sanvicente et al. INTERNATIONAL JOURNAL OF THERMAL SCIENCES
- Computational fluid dynamic analysis of core bypass flow phenomena in a prismatic VHTR
- (2010) Hiroyuki Sato et al. ANNALS OF NUCLEAR ENERGY
- On the onset of turbulence in natural convection on inclined plates
- (2010) A. Rodríguez-Sevillano et al. EXPERIMENTAL THERMAL AND FLUID SCIENCE
- Scaling analysis for the high temperature Gas Reactor Test Section (GRTS)
- (2009) J.N. Reyes et al. NUCLEAR ENGINEERING AND DESIGN
- Numerical investigation of a heat transfer within the prismatic fuel assembly of a very high temperature reactor
- (2008) Nam-il Tak et al. ANNALS OF NUCLEAR ENERGY
Find the ideal target journal for your manuscript
Explore over 38,000 international journals covering a vast array of academic fields.
SearchBecome a Peeref-certified reviewer
The Peeref Institute provides free reviewer training that teaches the core competencies of the academic peer review process.
Get Started