The “supercritical CO2 heat removal system”, sCO2-HeRo, safely, reliably and efficiently removes residual heat from nuclear fuel. Since this system is powered by the decay heat itself it can be considered as an excellent backup cooling system for the reactor core or the spent fuel storage in the case of a station blackout and loss of ultimate heat sink or accidents that are beyond design. sCO2-HeRo is a very innovative reactor safety concept as it improves the safety of both currently operating and future BWRs (Boiling Water Reactors) and PWRs (Pressurized Water Reactors) through a self-propellant, self-sustaining and self-launching, highly compact cooling system using supercritical carbon dioxide.
The thermal-hydraulics Simulations and Experiments for the Safety Assessment of Metal cooled reactor (SESAME) project supports the development of European liquid metal cooled reactors (ASTRID, ALFRED, MYRRHA, SEALER). The project focusses on pre-normative, fundamental, safety-related, challenges for these reactors.
SAMOFAR (Safety Assessment of the Molten Salt Fast Reactor) is one of the major Research and Innovation projects in the Horizon 2020 Euratom research programme. The grand objective of the project is to deliver a breakthrough in nuclear safety and nuclear waste management to make nuclear energy truly safe and sustainable. To this end, a new type of nuclear reactor, the Molten Salt Fast Reactor (MSFR), has been developed, whose key safety features will be demonstrated in the project.
Supercritical fluids are one of the main workhorses of modern industry. The unique properties of these fluids enable us to produce better products and make processes much more efficient. Despite their widespread application, predicting the heat transfer of these fluids has remained an unsolved problem until today. One has observed unexpected large temperature peaks in industrial processes and equipment that could not be explained by standard models or correlations. This project therefore aims to develop an accurate, physically sound design correlation for heat transfer in supercritical fluids
A variation of the aqueous production method is investigated by using a uranium salt dissolved in water that is guided along a reactor core. To this purpose, a PhD student works in the field of neutronics (numerical), fluid mechanics (numerical), testing and optimizing of different separation methods for fission uranyl solutions (experimental) and microfluidics (experimental and numerical)
Martin Rohde (2018)