The 11th NEA Expert Group on Reactor Coolants and Components Technology (EGCoCoT) meeting was held in Paris on 22-23 April 2025.
Published date:
25 April 2025
The project held Nuclear Data Week to discuss progress of the ongoing activities.
Published date:
23 April 2025
Project members met in France and online to discuss the ongoing and future activities.
Published date:
23 April 2025
Published date:
14 April 2025
14 -
18 April 2025
Jozef Stefan Institute (JSI), Reaktorski center Podgorica, Brinje 40, 1262 Dol pri Ljubljani, Ljubljana, Slovenia
Published date:
31 March 2025
NEA/NSC/R(2024)2
Efforts to enhance the safety, sustainability and economic efficiency of nuclear energy are driving international research into advanced nuclear fuel cycles. A key component of these efforts is parti...
Published date:
11 April 2025
To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...
Published date:
7 April 2025
Image: QUENCH facility at KIT. Court. KIT.
The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...
Published date:
2 April 2025
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 ...
Published date:
2 April 2025
31 March 2025 -
3 April 2025
CSIC HQ, Aula Magna Calle de Serrano 117, 28006, Madrid, Spain
The OECD Nuclear Energy Agency (NEA) and Ciemat co-organised the Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7), with the support of industry, Newcleo...
Published date:
28 April 2025
NEA expert group discusses advanced fuel cycle scenarios
Published date:
4 March 2025
NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest issues concerning the economic and technical aspects of nuclear energy, nuclear safety and ...
Published date:
25 February 2025
International experts discussed plans for an upcoming workshop.
Published date:
19 February 2025
17 -
21 February 2025
NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France), remote access only under exceptional circumstances
Published date:
27 November 2024
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...
Published date:
11 February 2025
Published date:
10 February 2025
The NEA Working Party on Nuclear Criticality Safety discussed ongoing and future activities.
Published date:
6 February 2025
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...
Published date:
6 February 2025
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...
Published date:
5 February 2025
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...
Published date:
4 February 2025
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.
Published date:
4 February 2025
DYMOND simulates the time-dependent behavior and evolution of the entire nuclear fuel cycle including mining, enrichment, fueling, reactors, reprocessing, waste management, disposal, etc.
Published date:
4 February 2025
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...
Published date:
4 February 2025
COSAC is used to study the flow and the storage of nuclear materials in a nuclear fleet composed of the following installations:
- mines
- fresh fuel manufacturing plants.
- reactors
- cooling pools
- spent f...
Published date:
4 February 2025
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...
Published date:
4 February 2025
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...
Published date:
4 February 2025
NMB4.0 is designed to provide flexibility and an all-in-one packaged nuclear fuel cycle simulation for users as open code. Various ideas have been implemented to improve user-friendliness. The main t...
Published date:
3 February 2025
TR_EVOL (Transition Evolution code) fuel cycle simulator is a tool dedicated to the study of mass balances of advanced transition electronuclear scenarios.
Published date:
31 January 2025
The Advanced Nuclear Cycle Code, ANICCA, is a nuclear fuel cycle simulation code (NFCSC) that has been developed by SCK-CEN as a flexible tool for nuclear fuel cycle studies. ANICCA is able to simula...
Published date:
31 January 2025
Once irradiated or “spent” nuclear fuel is unloaded from a reactor it is usually stored at the reactor site for between five and ten years. It is then ready for long-term storage or for reprocessing ...
Published date:
24 January 2025
Several applications of interest in nuclear criticality safety involve random media, which are media where the geometrical and/or material properties can only be described by assigning some probabili...
Published date:
24 January 2025
The JEFF Nuclear Data Week took place on 25-29 November 2024.
Published date:
12 December 2024
NEA/WKP(2024)4
Under the guidance of the Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor ph...
Published date:
12 December 2024
The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) and its expert groups co-ordinate benchmark activities on Reactor Single- and Multi-Physics. The benchmark ac...
Published date:
11 December 2024
NEA released the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook which contains criticality safety benchmark specifications
Published date:
21 November 2024
Published every year, the NEA Annual Report includes an overview of NEA's activities and publications produced during the year, as well as the latest developments in nuclear energy sector around the ...
Published date:
20 November 2024
Publié chaque année, le Rapport annuel de l’AEN présente un aperçu des activités et publications de l’AEN pour une année donnée, ainsi que les derniers développements du secteur de l’énergie nucléair...
Published date:
20 November 2024
Fluoride salt-cooled high-temperature reactors (FHRs), cooled with liquid (molten) salt, fueled with TRISO-based fuel are a potential molten salt reactor (MSR) design.
Published date:
19 November 2024
The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allo...
Published date:
12 November 2024
Members of the NEA joint project Thermodynamics of Advanced Fuels - International Database (TAF-ID) met on 23-25 October 2024.
Published date:
8 November 2024
NEA/WKP(2024)5
The Serpent-2 software is a three-dimensional continuous-energy neutron and photon transport code, developed at the Technical Research Centre of Finland (VTT) (Leppänen, 2015), and is one of the most...
Published date:
7 November 2024
TCOFF-2 members met to discus the ongoing activities.
Published date:
16 October 2024
Published date:
4 October 2024
NEA/WKP(2024)2
Under the auspices of the Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Reactor Systems (WPRS) has been established to study reactor physics, ...
Published date:
4 October 2024
The NEA Working Party on Nuclear Criticality Safety (WPNCS) and its subgroups held their annual plenary meetings.
Published date:
2 October 2024
The Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) studies advanced nuclear fuel cycles, including fuel cycle scenarios, innovative fuels and materials, separation chemistry, waste...
Published date:
1 October 2024
The Working Party on Nuclear Criticality Safety (WPNCS) deals with technical and scientific issues relevant to criticality safety. Specific areas of interest include (but are not limited to) investig...
Published date:
1 October 2024
SFCOMPO 2.0 (Spent Fuel Isotopic Composition) is a relational database designed to facilitate the search and visualisation of experimental assay data of spent nuclear fuel.
Published date:
1 October 2024
The NEA delegation travelled to Bulgaria to take part in “Sustainable Nuclear Innovations.”
Published date:
21 August 2024
International benchmark of solvent extraction codes and process modelling applied to hydro-processes focuses on the modelling of PUREX (TBP-based extractions) systems with uranium and nitric acid as ...
Published date:
12 August 2024