A Review of the Scaling Study of the CANDU-6 Moderator Circulation Test Facility

ISSN Print: 2327-588X
ISSN Online: 2327-5901
www.scirp.net/journal/jpee
E-mail: [email protected]

Citations

"A Review of the Scaling Study of the CANDU-6 Moderator Circulation Test Facility"
written by Bo Wook Rhee, Hyoung Tae Kim,
published by Journal of Power and Energy Engineering, Vol.2 No.9, 2014

has been cited by the following article(s):

[1]	Computational Fluid Dynamic Simulation of the Moderator Flow in CANDU-6 Nuclear Reactors
	2017

[2]	Étude thermo-hydraulique de l'écoulement du modérateur dans le réacteur CANDU-6
	2016

[3]	CFD analysis of moderator flow and temperature fields inside a vertical calandria vessel of nuclear reactor
	Nuclear Engineering and Design, 2015

Top