Abstract The High Temperature Gas-cooled Reactor (HTGR) is an advanced reactor design
being pursued by several different domestic and international organizations due to its high …

This paper investigates comprehensively the operational dynamics of a thermochemical
heat storage (TCHS) reactor for low‐temperature applications using polyaluminum sulfate …

ABSTRACT RELAP5-3D, developed by Idaho National Laboratory (INL), incorporates a
mathematical representation of thermal-hydraulic phenomena compiled for the simulation …

Abstract The Korea Atomic Energy Research Institute (KAERI) has developed the Core
Reliable Optimization and thermofluid Network Analysis (CORONA) code for core …

Fuel assembly bypass flow is the coolant flow through the guide thimble and the instrument.
The fuel assembly bypass flow should be limited to ensure that there is sufficient coolant in …

The very high-temperature gas-cooled reactor (VHTR) is a Gen IV nuclear reactor that has
been developed from the high-temperature gas-cooled reactor (HTGR) with the aim for …

Korea Atomic Energy Research Institute (KAERI) has developed CORONA (Core Reliable
Optimization and thermo-fluid Network Analysis) code for core thermo-fluid analysis of …

The core of the prismatic very high temperature reactor (VHTR) consists of hexagonal
prismatic fuel blocks and reflector blocks made of graphite. Therefore, there are interstitial …