Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...

In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...

This benchmark focuses on FHR reactors with plates and triso fuel. Several phases are planned, starting with neutronics on a simple fuel element simulation without burn-up, and gradually extending to...

The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...

The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

In 2013, the Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) published a report that investigated fuel depletion effects in a pressurised water reactor (PWR). This was entitled...