The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems was hosted by CEA Cadarache in Aix-en-Provence. During the week of 30 May to 3 June...
Thermodynamic databases and accident prevention
This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).
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...
Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.
The annual Benchmark Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted by the Italian National Agency for New Technologies, Energy and Sus...
The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues.
The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.
10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.
The EGMUP Task Force on artificial intelligence and machine learning will design benchmark specifications to evaluate the performance of AI/ML in multi-physics modeling and simulation of reactor syst...
Experts from 16 countries met on 13-15 September for the 24th annual Working Group on Fuel Safety GFS meeting in Paris.
The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...
The benchmark will predict the Critical Heat Flux (CHF).
FIDES-II member assembled at the Japan Atomic Energy Agency (JAEA) in Mito, Japan.
The International School on Simulation of Nuclear Reactor Systems (SINUS) provides hybrid, hands-on-training encompassing multiphysics modelling and simulation (M&S) and associated validation, verifi...
Under the guidance of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance,...
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 meeting marked an important transition for the framework with the launch of four new Joint Experimental Programmes (JEEPs).
Many of the failures that occur in nuclear fuel rods in light water reactors around the world are caused by the phenomenon of mechanical interaction between pellets and cladding (PCMI). The process i...