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    News
    Discussing advances in reactor coolants and component technologies

    The 11th NEA Expert Group on Reactor Coolants and Components Technology (EGCoCoT) meeting was held in Paris on 22-23 April 2025.

    Nuclear fuel News brief Fuel studies Nuclear science EGCoCoT Liquid metal reactors Nuclear science Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 25 April 2025
    News
    Preparing JEFF nuclear data library update for fission and fusion applications

    The project held Nuclear Data Week to discuss progress of the ongoing activities.

    News brief Nuclear energy data Nuclear science Nuclear data Data Bank Databases Codes and programs …
    Published date: 23 April 2025
    News
    FIDES-II: Ensuring the competences for irradiation experiments

    Project members met in France and online to discuss the ongoing and future activities.

    Fuel in nuclear safety Nuclear fuel News brief Fuel studies Nuclear science FIDES Nuclear safety research Reactor fuel performance Safety research Nuclear science Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 23 April 2025
    Activity
    SINBAD - Shielding Integral Benchmark Archive and Database

    https://www.oecd-nea.org/tools/ierequest/start/package/NEA-1939%2501The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for more than 100 reactor shielding, ...

    Transport Experiments Radiation Databases Radiation transport and shielding Reactor physics Integral experiments Verification and validation Validation SINBAD Benchmark …
    Published date: 14 April 2025
    Event
    2025 Meetings of the ICSBEP, IRPhEP, SFCOMPO Technical Review Groups and the SINBAD Task Force
    14 - 18 April 2025
    Jozef Stefan Institute (JSI), Reaktorski center Podgorica, Brinje 40, 1262 Dol pri Ljubljani, Ljubljana, Slovenia

    The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP), International Reactor Physics Experiments Evaluation Project (IRPhEP), International Assay Data of Spent Nuclear Fuel D...

    Nuclear science ICSBEP WPRS Radiation transport and shielding IRPhEP Reactor physics Criticality safety NSC Verification and validation SINBAD Nuclear science Benchmark …
    Published date: 31 March 2025
    NEA Document
    Summary Report of the 16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT)
    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...

    Nuclear science Nuclear fuel cycle Partitioning and transmutation
    Published date: 11 April 2025
    Activity
    Deterministic Time-Dependent Neutron Transport Benchmark without Spatial Homogenisation (C5G7-TD)

    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...

    Transport Verification and validation Verification Radiation Uncertainty quantification Uncertainty analysis Benchmark Reactor physics …
    Published date: 7 April 2025
    Joint project
    QUENCH-ATF project

    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...

    Nuclear science Nuclear safety research Joint project Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 2 April 2025
    Joint project
    Second Framework for Irradiation Experiments (FIDES‑II)

    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 ...

    Fuel in nuclear safety Nuclear fuel Nuclear science FIDES Nuclear safety research Accident tolerant fuels Reactor fuel performance …
    Published date: 2 April 2025
    Event
    Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7)
    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...

    Material science Structural materials Nuclear science Materials science WPFM Nuclear science …
    Published date: 28 April 2025
    News
    NEA expert group discusses advanced fuel cycle scenarios

    NEA expert group discusses advanced fuel cycle scenarios

    Nuclear fuel WPFC News brief NSC EGAFCS Nuclear fuel cycle Fuel cycle physics and chemistry …
    Published date: 4 March 2025
    Activity
    NEA News

    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 ...

    Nuclear law Human aspects of nuclear safety Radiological protection Nuclear science Nuclear economics Nuclear technology Decommissioning and legacy management Radioactive waste management Nuclear safety research NEA News publication Nuclear energy and climate change Nuclear safety regulation …
    Published date: 25 February 2025
    News
    Molten salt reactor fuel cycles: Towards a common language

    International experts discussed plans for an upcoming workshop.

    News brief Nuclear science Molten salt reactors Nuclear science Nuclear fuel cycle EGFRW Fuel cycle physics and chemistry …
    Published date: 19 February 2025
    Event
    22nd Meeting of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)
    17 - 21 February 2025
    NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France), remote access only under exceptional circumstances

    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...

    Nuclear science EGRFP EGRRS WPRS Multiphysics Radiation transport and shielding Thermal hydraulics and mechanics EGTHM Reactor physics Reactor fuel performance EGMUP NSC Nuclear science …
    Published date: 27 November 2024
    Activity
    NEA Global Forum on Nuclear Education, Science, Technology and Policy

    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...

    Nuclear science Education Human resources development (HRD) Global Forum International co-operation Training Nuclear knowledge management …
    Published date: 11 February 2025
    Other
    International School on Simulation of Nuclear Reactor Systems (SINUS) - Training the next generation of reactor physicists
    SINUS Nuclear science Education WPRS
    Published date: 10 February 2025
    News
    Experts discuss the latest in nuclear criticality safety

    The NEA Working Party on Nuclear Criticality Safety discussed ongoing and future activities.

    News brief Criticality safety Nuclear science Criticality WPNCS Nuclear science …
    Published date: 6 February 2025
    Activity
    International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook

    The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...

    Modelling and simulation Criticality safety Verification and validation Verification Benchmark …
    Published date: 6 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue

    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...

    Nuclear fuel Nuclear science Nuclear data Reactor physics Reactor physics Small modular reactors Advanced reactor systems Nuclear innovation Fuel cycle technology Nuclear science Nuclear fuel cycle Fuel cycle physics and chemistry Fuel cycle economics Sustainable development and nuclear energy …
    Published date: 5 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - NFCSS: The Nuclear Fuel Cycle Simulation System

    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...

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - FAMILY-21

    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.

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - DYMOND: Dynamic Model of Nuclear Deployment

    DYMOND simulates the time-dependent behavior and evolution of the entire nuclear fuel cycle including mining, enrichment, fueling, reactors, reprocessing, waste management, disposal, etc.

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - COSI

    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...

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - COSAC

    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...
    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - CLASS: Core Library for Advanced Scenario Simulation

    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...

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - VISION

    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...

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 4 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - NMB: Nuclear Material Balance

    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...

    Nuclear fuel Optimisation of radioactive waste management EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 3 February 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - TR_EVOL: Transition Evolution code

    TR_EVOL (Transition Evolution code) fuel cycle simulator is a tool dedicated to the study of mass balances of advanced transition electronuclear scenarios.

    Nuclear fuel EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 31 January 2025
    Activity
    Nuclear Fuel Cycle Codes Catalogue - ANICCA

    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...

    Nuclear fuel WPFC Nuclear data EGAFCS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry …
    Published date: 31 January 2025
    Publications and Reports
    Unlocking the Hidden Value of Nuclear Fuel: The Societal Benefits of Diverse Material Recycling

    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 ...

    English WPFC Nuclear science Spent fuel Nuclear science Nuclear fuel cycle EGFRW …
    Published date: 24 January 2025
    Publications and Reports
    Criticality Calculations in Random Geometries

    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...

    English Nuclear science Criticality WPNCS Nuclear science …
    Published date: 24 January 2025
    News
    Working with industry to develop JEFF data library

    The JEFF Nuclear Data Week took place on 25-29 November 2024.

    News brief Nuclear energy data Nuclear data Data Bank Databases …
    Published date: 12 December 2024
    NEA Working Paper
    Experimental Data Requirements for Fuel Performance Modelling
    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...

    Nuclear fuel Fuel studies NSC Nuclear science EGRFP WPRS Nuclear science Reactor physics Reactor fuel performance …
    Published date: 12 December 2024
    Activity
    Benchmark Activities on Reactor Single- and Multi-Physics of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)

    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...

    Multi-physics simulations Boiling water reactors Nuclear science Light water reactors Artificial Intelligence Liquid metal reactors WPRS Advanced reactors Reactor physics Machine Learning Verification and validation Uncertainty quantification Benchmark Pressurised water reactors …
    Published date: 11 December 2024
    News
    New release: The International Handbook of Evaluated Criticality Safety Benchmark Experiments

    NEA released the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook which contains criticality safety benchmark specifications

    Modelling and simulation Criticality safety Nuclear science Criticality Verification and validation Validation ICSBEP Benchmark …
    Published date: 21 November 2024
    Publications and Reports
    2023 NEA Annual Report

    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 ...

    English Nuclear law Human aspects of nuclear safety Radiological protection Nuclear science Nuclear economics Nuclear technology Decommissioning and legacy management Radioactive waste management Nuclear safety research Nuclear energy and climate change Annual Report Nuclear safety regulation …
    Published date: 20 November 2024
    Publications and Reports
    2023 AEN Rapport annuel

    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...

    Nuclear law Human aspects of nuclear safety French Radiological protection Nuclear science Nuclear economics Nuclear technology Decommissioning and legacy management Radioactive waste management Nuclear safety research Nuclear energy and climate change Nuclear safety regulation …
    Published date: 20 November 2024
    Activity
    Fluoride Salt-Cooled High-Temperature Reactor (FHR) Benchmark

    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.

    Nuclear science Molten salt reactors Verification Reactor physics
    Published date: 19 November 2024
    Activity
    International Criticality Safety Benchmark Evaluation Project (ICSBEP)

    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...

    Criticality safety Nuclear science Criticality WPNCS ICSBEP …
    Published date: 12 November 2024
    News
    NEA joint project Thermodynamics of Advanced Fuels – International Database marks 10 years

    Members of the NEA joint project Thermodynamics of Advanced Fuels - International Database (TAF-ID) met on 23-25 October 2024.

    Structural materials Fuel studies Nuclear science Materials science Thermodynamic data TAF-ID …
    Published date: 8 November 2024
    NEA Working Paper
    Automated Conversion of International Criticality Safety Benchmark Models: Developing a Reproducible Serpent-2 Model Repository from MCNP Inputs
    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...

    WPEC Nuclear science Validation Nuclear data processing
    Published date: 7 November 2024
    News
    Improving thermodynamic modelling for the analysis of severe accidents

    TCOFF-2 members met to discus the ongoing activities.

    News brief Nuclear science Fission products Fukushima Nuclear safety research Joint project Safety research Thermodynamic data Nuclear science Accident Tolerant Fuels …
    Published date: 16 October 2024
    Other
    Second NEA Framework for Irradiation Experiments (FIDES-II): Sustaining multinational nuclear fuel and materials testing capacities for safety, industry and science
    Nuclear science FIDES Nuclear science
    Published date: 4 October 2024
    NEA Working Paper
    Fluoride-salt High-temperature Reactor (FHR) Reactor Physics Calculations Benchmark
    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, ...

    English Nuclear science EGRPANS WPRS Nuclear science Benchmark …
    Published date: 4 October 2024
    News
    Discussing latest developments in nuclear criticality safety

    The NEA Working Party on Nuclear Criticality Safety (WPNCS) and its subgroups held their annual plenary meetings.

    News brief Criticality safety Nuclear science Criticality WPNCS Nuclear science …
    Published date: 2 October 2024
    Activity
    Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC)

    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...

    Nuclear fuel WPFC Fuel studies Nuclear science Liquid metal reactors Thermal hydraulics and mechanics Reactor fuel performance NSC Nuclear innovation Fuel cycle technology Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 1 October 2024
    Activity
    Working Party on Nuclear Criticality Safety (WPNCS)

    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...

    Criticality safety NSC Nuclear science Criticality WPNCS …
    Published date: 1 October 2024
    Activity
    SFCOMPO 2.0 (Spent Fuel Isotopic Composition)

    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.

    Criticality safety Verification and validation Databases
    Published date: 1 October 2024
    News
    Fostering innovative approaches to Bulgaria's nuclear energy development

    The NEA delegation travelled to Bulgaria to take part in “Sustainable Nuclear Innovations.”

    News brief Bulgaria Nuclear science Nuclear innovation Nuclear science Innovation Education and capacity building …
    Published date: 21 August 2024
    Activity
    International Benchmarking Exercise on Solvent Extraction Codes and Process Modelling

    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 ...

    Nuclear science Nuclear science Fuel cycle physics and chemistry
    Published date: 12 August 2024
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