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.
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
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...
The NEA Working Party on Nuclear Criticality Safety (WPNCS) held its bi-annual meetings in June 2023
Co-organised with the UK Atomic Energy Authority, the course took place on 20-22 June 2023.
High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...
TCOFF-2 members discuss future activities.
The NEA workshop gathered experts to discuss the challenges and opportunities related to the demise of zero power reactors.
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...
10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.
Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.
The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.
The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.
WPFM held meetings on 23-25 May 2023.
The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues.
Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...
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...
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...
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...