The next annual Benchmarks Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) will be hosted by the Department of Engineering of the University of ...
The NEA Working Group on New Technology (WGNT) is organising a hybrid international workshop on 3–5 June 2025. The workshop will be hosted at the US Nuclear Regulatory Commission headquarters.
The NEA will organise the third International School on Simulation of Nuclear Reactor Systems (SINUS) on the topic of Reactor single- and multi-physics simulations based on Light Water Reactor (LWR) ...
The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP), International Reactor Physics Experiments Evaluation Project (IRPhEP), International Assay Data of Spent Nuclear Fuel D...
The OECD Nuclear Energy Agency (NEA) and CIEMAT are co-organising the Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7). The workshop will be held in Mad...
International experts discussed plans for an upcoming workshop.
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 performanc...
New NEA initiative on AI was announced at the World Governments Summit.
The NEA Global Forum on Nuclear Education, Science, Technology and Policy (the Global Forum on Nuclear Education) is a framework for sustained co-operation and for enabling a long-term dialogue among...
The NEA Working Party on Nuclear Criticality Safety discussed ongoing and future activities.
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...
This web page is intended for the description of the nuclear fuel cycle codes that have been used in the recent activities of the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS), under the gui...
The Nuclear Fuel Cycle Simulation System (NFCSS) is a scenario based computer simulation tool, implemented in a web based platform, for studying various options of nuclear fuel cycle for nuclear powe...
The FAMILY-21 code is a stand-alone simulation code developed to quantitatively indicate reactor systems and nuclear fuel cycle systems adaptable to future uncertain nuclear needs.
DYMOND simulates the time-dependent behavior and evolution of the entire nuclear fuel cycle including mining, enrichment, fueling, reactors, reprocessing, waste management, disposal, etc.
COSI is a calculation code that simulates nuclear reactor fleets and the associated fuel cycle facilities over several decades. This tool is developed by the SPRC (Reactor Physics and fuel Cycle Serv...
COSAC is used to study the flow and the storage of nuclear materials in a nuclear fleet composed of the following installations:
Since 2012, CLASS is developed CNRS/IN2P3 (Centre National de la Recherche Scientifique / Institut National de Physique Nucléaire et de Physique des Particules) with initial support from IRSN (Instit...
The VISION Nuclear Fuel Cycle Simulation Model is a system dynamics model that captures all aspects of the nuclear fuel cycle, from mining of ore to the ultimate disposal of spent fuel and high-level...