Bypass Flow Resistance in Prismatic Gas-Cooled Nuclear Reactors

High Temperature Gas Cooled Reactors

GAS COOLED REACTORS (Session 6) Chairpersons

The High Temperature Gas-cooled Reactor (HTGR) is particularly attractive due to its capability of producing high temperature helium gas and inherent safety characteristics. These interesting aspects make HTGR worthy of discussion on the future advanced reactors. The Japanese interest in the HTGR has resulted in the construction of the High Temperature Engineering Test Reactor (the HTTR) at the...

Large Eddy Simulation in Pebble Bed Gas Cooled Core Reactors

A High Temperature Gas-cooled Reactor (HTGR) is one of the renewed reactor designs to play a role in nuclear power generation. This reactor design concept is currently under consideration and development worldwide. The combination of coated particle fuel, inert helium gas as coolant and graphite moderated reactor makes possible to operate at high temperature yielding a high efficiency. In this ...

Supercritical Water-cooled Nuclear Reactors: Review and Status

Modern concepts of nuclear reactors cooled with supercritical water are presented together with a short history. The supercritical water-cooled CANDU ((CANada Deuterium Uranium) is a registered trademark of AECL) reactor concept is fully discussed. Also, thermophysical properties at critical and supercritical pressures as well as heat transfer and hydraulic resistance at these conditions are pr...

Detailed Reaction Kinetics for CFD Modeling of Nuclear Fuel Pellet Coating for High Temperature Gas-Cooled Reactors