Fuel development for gas-cooled fast 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...

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

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 ...

The Economics of Alternative Fuel Cycles on Sodium - Cooled Fast Reactors and Uncertainty and Sensitivity Analysis of Cost Estimates

Previous work was done to create a baseline capital cost model for the SFR in which case studies were performed to identify ways to decrease the capital costs while maintaining safety and performance. This thesis expands on the capital cost model to include uncertainty analysis, as well as performing qualitative cost evaluations for the fuel cycle and O&M costs. An uncertainty model was develop...