Design features of water-cooled research reactors

Mitigation of hydrogen hazards in water cooled power reactors

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...

High Temperature Gas Cooled Reactors

Validation of Reactor Physics-thermal Hydraulics Coupled Calculation in Water-cooled Research Reactors with Laminar Flow Regimes

A collaboration between the University of Florida and the Swiss Federal Institute of Technology, Lausanne (EPFL) has been formed to develop and validate detailed coupled multiphysics models of the zero-power (100 W) CROCUS reactor at EPFL and the 100 kW University of Florida Training Reactor, for the comprehensive analysis of the reactor behavior under transient (neutronic or thermal-hydraulic ...

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...