EGPRS Task Force members met on 3 April 2023.
Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...
International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.
Thermodynamic databases and accident prevention
Expert groups on structural and fuel materials meet to advance materials science activities
The WPRS met from 20-24 February 2023.
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 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...
Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM) addresses materials science aspects of nuclea...
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.
The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countrie...
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.