Accident safety analysis of flow blockage in an assembly in the JRR-3M research reactor using system code RELAP5 and CFD code FLUENT

Experimental Study of Differences in DNB Heat Flux between Upflow and Downflow in Vertical Rectangular Channel

Yukio SUDO, Keiichi Miyata, Hiromasa Ikawa et al. · Journal of Nuclear Science and Technology · 1985 · 69 citations

Engineering, Nuclear Engineering, Heat Transfer +16

Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core

Martina Adorni, A Bousbia Salah, Tewfik Hamidouche et al. · Annals of Nuclear Energy · 2005 · 63 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +13

Flow blockage analysis of a channel in a typical material test reactor core

Qing Lü, Suizheng Qiu, G.H. Su · Nuclear Engineering and Design · 2008 · 62 citations

Engineering, Materials Engineering, Nuclear Engineering +14

Experimental study of differences in DNB heat flux between upflow and downflow in vertical rectangular channel.

Yukio SUDO, Keiichi Miyata, Hiromasa Ikawa et al. · Journal of Nuclear Science and Technology · 1985 · 55 citations · Full text

Engineering, Nuclear Engineering, Heat Transfer +16

CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core

Amgad Salama, Salah El-Din El-Morshedy · Annals of Nuclear Energy · 2011 · 54 citations

Engineering, Computational Engineering, Nuclear Engineering +17