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 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...
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...
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:
