The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
NEST Alumni share valuable lessons from their fellowships
The NEA thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H), supervised by the Expert Group on Reactor Core Thermal-Hydraulics and Mechanic...
Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...
Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...
This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...
Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.
In the early decades of nuclear reactor development, many countries built and operated zero-power facilities in which many different critical arrangements of materials were studied. These flexible ex...
The NEA workshop gathered experts to discuss the challenges and opportunities related to the demise of zero power reactors.
Burn-up credit is a safety approach that accounts for the reduction in the reactivity of configurations with spent nuclear fuel due to the change in their composition after irradiation.
The expert group monitored the feedback from version 0 of the Lead-bismuth eutectic (LBE) handbook, collected, analysed and checked the consistency of expected new results from ongoing heavy liquid m...
The task force developed best practice guidelines by performing a benchmark study on thermo-hydraulic modelling of heavy liquid metal coolant, e.g. lead and lead-bismuth eutectic (LBE) alloy.
Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, an...
The expert group conducts joint and comparative studies to support the development, selection and characterisation of innovative structural materials that can be implemented in advanced nuclear fuel ...
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Fuel Recycling and Waste Technology (EGFRW) focuses on the separation processes releva...
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Reactor Coolants and Components Technology (EGCoCoT) undertakes activities to collect,...
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS) studies the needs associated with the transitio...
The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiments Evaluation Project (IRPhEP) Technical Review Groups, and the Shielding Int...
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Innovative Fuel Elements (EGIFE) conducts joint and comparative studies to identify te...
