Several passive safety systems are included in the design of the Economic Simplified
Boiling Water Reactor (ESBWR) safety system. To investigate the capability of the ESBWR …

Abstract The RELAP5/MOD3. 3 code was used to simulate a Main Steam Line Break (MSLB)
Loss of Coolant Accident (LOCA) on a Generation III type Reactor with passive safety …

PUMA-E is an integral test facility, which is used for extensive experimental investigations to
study the behavior of Boiling Water Reactor (BWR) plants under accident conditions. The …

Numerical and experimental analyses of open channel natural convection heat transfer of a
finned plate were carried out. By varying the fin spacing, the heat transfer rates were …

Lately, natural circulation has become an exciting topic because it has been proposed and
applied in some advanced nuclear reactors as a passive safety system. The aim of the …

ABSTRACT A computer code has been written to predict interfacial area transport within the
framework of the two-fluid model. The suitability of various constitutive models was …

The passive nuclear reactor cooling system has become a fascinating topic, especially since
the nuclear incident in Fukushima Daiichi, Japan. This study proposed to review a natural …

Molten salt has attracted the attention of researchers, especially as a coolant because of its
characteristics. This study aimed to analyse the transient and steady-state of the natural …

Molten salt has been widely known to have much utilization, both as thermal storage and as
a coolant in several energy generation systems. This study aimed to determine the …

Abstract A postulated Large Break Loss-Of-Coolant-Accident (LB LOCA) on a generic
Generation III+ Boiling Water Reactor (BWR) equipped with passive safety systems has …