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    News
    Discussing scientific issues in the design and qualification of reactor systems

    The WPRS met from 20-24 February 2023.

    News brief Nuclear science WPRS Multiphysics Nuclear science Benchmark Multiphysics …
    Published date: 17 March 2023
    Event
    Kick-off meeting preparation for the Framework for Irradiation Experiments (FIDES) Joint Experimental Programmes (JEEPs)
    3 - 5 September 2019
    OECD Conference Centre, CC15, 2 rue André Pascal, 75016, Paris, France

    The continued evolution of fuel and materials technology, fuel performance, optimisation of operational limits, material ageing, failure limits, etc. requires experimental evidence obtained from test...

    Nuclear fuel Material science Nuclear science Materials science Experimental needs …
    Published date: 27 February 2020
    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...

    Nuclear science WPRS Reactor physics
    Published date: 16 March 2023
    Event
    WPRS Benchmarks Workshop 2023
    22 - 26 May 2023
    Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy

    The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted in 2023 by the Italian National Agency for New Technologies, Energy ...

    Reactor physics Nuclear science Multiphysics Nuclear science Benchmark Thermal hydraulics and mechanics Reactor physics Reactor fuel performance Multiphysics …
    Published date: 16 March 2023
    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 institution...

    Fuel in nuclear safety Nuclear fuel Nuclear science FIDES Nuclear safety research Accident tolerant fuels Reactor fuel performance …
    Published date: 14 March 2023
    Activity
    Expert Group on Reactor Fuel Performance (EGRFP)

    Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...

    Nuclear fuel Reactor physics EGRFP Reactor physics
    Published date: 8 March 2023
    Activity
    FIDES-II Cross-Cutting Pillars

    The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues. 

    Fuel in nuclear safety Nuclear science Nuclear safety research Reactor fuel performance
    Published date: 7 March 2023
    Activity
    Burst Fission Gas Release (FGR) Benchmark of the Expert Group on Reactor Fuel Performance (EGRFP)

    This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).

    Nuclear science Validation EGRPF WPRS Benchmark Reactor fuel performance …
    Published date: 7 March 2023
    Subtopic
    Reactor fuel performance

    Understanding fuel performance is a key condition for successful reactor operation. Scientific knowledge in this domain was conceived by experimental tests encoded into software routines to ensure ac...

    Reactor physics Fuel studies Nuclear science Reactor physics
    Published date: 10 December 2020
    Activity
    Expert Group on Structural Materials (EGSM)

    Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Structural Materials (EGSM) focuses on materials science aspe...

    Material science Structural materials NSC Nuclear science Materials science WPFM Nuclear science …
    Published date: 3 March 2023
    Activity
    Expert Group on Fuel Materials (EGFM)

    Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Fuel Materials (EGFM) focuses on materials science aspects of...

    Nuclear fuel Material science NSC Nuclear science Materials science WPFM Nuclear science Accident tolerant fuels …
    Published date: 3 March 2023
    Activity
    Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM)

    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...

    Nuclear fuel Material science Structural materials NSC Nuclear science Materials science WPFM Nuclear science Accident tolerant fuels …
    Published date: 3 March 2023
    Subtopic
    Reactor physics

    Questions relating to the space, time end energy distribution of neutrons and radiation in different media are the domain of reactor physics.

    Reactor physics Verification and validation Fast reactor Benchmark Advanced reactors Reactor physics …
    Published date: 2 December 2019
    NEA Document
    Existing Practices for Multi-physics Validation: Report on Sub-Task 3, Task Force 2
    NEA/NSC/R(2019)7

    The modelling and simulation of nuclear systems allow scientists and engineers to probe aspects of the operation of these systems beyond what has been precisely measured. This has numerous applicatio...

    Reactor physics Nuclear science WPRS Multiphysics Nuclear science Benchmark Reactor physics Multiphysics EGMUP …
    Published date: 11 October 2022
    Topic
    Nuclear science

    Nuclear science is the study of the atomic nuclei and their application, including in nuclear power plants, atomic theory and radiation.

    Nuclear science
    Published date: 2 December 2019
    News
    Expert groups on structural and fuel materials meet to advance materials science activities

    Expert groups on structural and fuel materials meet to advance materials science activities

    Material science News brief Fuel studies Nuclear science Materials science WPFM Databases Accident tolerant fuels …
    Published date: 24 February 2023
    News
    Improving thermodynamic databases and materials modelling for the analysis and prevention of nuclear accidents

    Thermodynamic databases and accident prevention

    News brief Fuel studies Nuclear science Materials science Fukushima Joint project Reactor fuel performance Material science Thermodynamic data TCOFF …
    Published date: 24 February 2023
    Subtopic
    Materials science

    Nuclear materials science investigates how corrosion, irradiation, thermal ageing and mechanical load may affect materials properties and potentially degrade their performance.

    Material science Modelling and simulation Model Nuclear science Materials science …
    Published date: 10 March 2020
    NEA Document
    State-of-the-Art Report on Multi-scale Modelling Methods
    NEA/NSC/R(2019)2
    Material science NSC Nuclear science Materials science Nuclear science …
    Published date: 29 September 2020
    Activity
    Working Party on Multi-scale Modelling of Fuels and Structural Materials for Nuclear Systems (WPMM)

    The Working Party on Multi-scale Modelling of Fuels and Structural Material for Nuclear Systems (WPMM) was established to deal with the scientific and engineering aspects of fuels and structural mate...

    Material science Structural materials WPMM Nuclear science Materials science …
    Published date: 4 March 2020
    Activity
    WPMM Expert Group on Multi-scale Modelling Methods (EGM3)

    Under the guidance of the Nuclear Science Committee (NSC) and under the mandate of the Working Party on Multi-scale Modelling of Materials (WPMM), the scope of the Expert Group on Multi-scale Modelli...

    Material science WPMM NSC Nuclear science Materials science EGM3 …
    Published date: 4 March 2020
    Event
    International Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors
    7 - 9 March 2017
    OECD Conference Centre, 2 rue André Pascal, Paris, France

    Advanced techniques for fuel modelling have progressed considerably in the last decade in part aided due to progress in high-performance computational capability. At the engineering scale, this has r...

    Material science WPMM NSC Nuclear science Materials science …
    Published date: 5 March 2020
    Other
    International Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors, 7-9 March 2017 - Announcement

    Announcement for the nternational Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors, 7-9 March 2017

    Material science WPMM NSC Nuclear science Materials science …
    Published date: 5 March 2020
    Other
    Participants - Kick-off meeting preparation for the Framework for Irradiation Experiments (FIDES) Joint Experimental Programmes (JEEPs)

    Kick-off meeting preparation for the Framework for Irradiation Experiments (FIDES) Joint Experimental Programmes (JEEPs) - List of participants

    Material science Nuclear science Materials science
    Published date: 27 February 2020
    Other
    NEA Framework for Irradiation Experiments (FIDES) flyer

    NEA Framework for Irradiation Experiments (FIDES) flyer (October 2019)

    Nuclear fuel Material science Nuclear science Materials science Experimental needs …
    Published date: 10 January 2020
    Joint project
    Dragon Project

    View of Dragon Reactor. Photo: AEA Technology.

    In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...

    Criticality safety Generation IV reactors Nuclear science Gas-cooled reactors Reactor physics …
    Published date: 14 October 2022
    Joint project
    Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)

    Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA

    TCOFF Phases

    First Phase (2017-2020)

    The TCOFF project established a framework for the exchange of technical...

    Nuclear science Fission products Fukushima Thermodynamic data Nuclear safety research Safety research …
    Published date: 7 December 2022
    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: 1 April 2022
    News
    Internationally recognised thermodynamic data to advance nuclear materials knowledge

    International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.

    News brief Fuel studies Nuclear science Materials science Nuclear data Joint project Material science Thermodynamic data TAF-ID …
    Published date: 24 February 2023
    Joint project
    Thermodynamics of Advanced Fuels – International Database (TAF-ID) public version

    The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:

    • oxide-carbide fuel (U-Pu-O-C, released Decemb...
    Material science Fuel studies Nuclear science Materials science Thermodynamics Thermodynamic data Databases TAF-ID Codes and programs …
    Published date: 23 February 2023
    Joint project
    Thermodynamics of Advanced Fuels - International Database (TAF-ID)

    On this page

    • Why is thermodynamic data for analyses involving nuclear fuel needed?
    • How is thermodynamic data calculated?
    • Available tools for thermodynamic calculations
    • Project organisation
    • TAF-ID i...
    Material science Structural materials Fuel studies Nuclear science Materials science Thermodynamic data TAF-ID …
    Published date: 23 February 2023
    Event
    International School on Simulation of Nuclear Reactor Systems (SINUS)
    1 - 23 May 2023
    Online training & in-person event on 22-23 May 2023 in Bologna, Italy

    The NEA will organise the first 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) ...

    Nuclear science Education WPRS Nuclear science Reactor physics …
    Published date: 20 February 2023
    NEA Document
    Statistical Tests for Diagnosing Fission Source Convergence and Undersampling in Monte Carlo Criticality Calculations
    NEA/NSC/R(2021)3

    Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...

    Criticality safety Monte Carlo method Nuclear science Criticality WPNCS Nuclear science …
    Published date: 17 February 2023
    NEA Document
    Burn-up Credit Criticality Studies: Benchmark Analyses for Pressurised Water Reactors
    NEA/NSC/R(2016)1
    English Nuclear science Criticality WPNCS WPRS Multiphysics Reactor physics Multiphysics EGMUP Reactor physics Criticality safety NSC Nuclear science …
    Published date: 23 February 2016
    Subtopic
    Thermal hydraulics and mechanics

    Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...

    Reactor physics Nuclear science Thermal hydraulics Verification and validation Verification Validation Benchmark Thermal hydraulics and mechanics Reactor physics …
    Published date: 10 December 2020
    Subtopic
    Criticality safety

    Criticality safety relates to accident prevention and protection from an uncontrolled nuclear fission chain reaction, or a criticality accident.

    Criticality safety
    Published date: 2 December 2019
    Subtopic
    Accident-tolerant fuels

    Accident-tolerant fuels may offer opportunities to enhance the safety and competitiveness of commercial nuclear power plants.

    Accident Tolerant Fuels
    Published date: 16 December 2019
    NEA Document
    Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes
    NEA/NSC/R(2015)9

    Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...

    English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Reactor physics Sodium-cooled reactor NSC EGPRS Nuclear science Benchmark …
    Published date: 5 November 2015
    NEA Document
    International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume II: Benchmark results of phase I Void distribution
    NEA/NSC/R(2015)4

    The objective of the benchmark was twofold. First, the benchmark aimed to evaluate currently available computational approaches in an effort to understand the strengths and weaknesses of current ther...

    English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark …
    Published date: 24 June 2015
    NEA Document
    International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume III: Departure from nucleate boiling
    NEA/NSC/R(2015)7

    The need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...

    English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
    Published date: 2 October 2015
    NEA Document
    MOx Depletion Calculation Benchmark
    NEA/NSC/R(2016)3

    In 2013, the Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) published a report that investigated fuel depletion effects in a pressurised water reactor (PWR). This was entitled...

    English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
    Published date: 14 June 2016
    NEA Document
    NEA Benchmark of the Modular High-Temperature Gas-Cooled Reactor 350 MW Core DesignVolumes I and II
    NEA/NSC/R(2017)4
    English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
    Published date: 6 December 2017
    NEA Document
    A Code to Code Benchmark for High-Temperature Gas-Cooled Reactor Fuel Element Depletion
    NEA/NSC/R(2019)1

    The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

    English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Multiphysics EGMUP Reactor physics Cogeneration NSC Gas-cooled reactors EGPRS Nuclear science Benchmark …
    Published date: 18 January 2019
    NEA Document
    Coupled Neutronic/Thermal-Fluid Benchmark of the MHTGR-350 MW Core Design: Results for Phase I Exercise 1
    NEA/NSC/R(2019)5
    Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
    Published date: 12 October 2020
    NEA Document
    Coupled Neutronic/Thermal-Fluid Benchmark of the MHTGR-350 MW Core Design: Results for the Lattice Physics Exercises
    NEA/NSC/R(2019)6

    The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...

    English Nuclear science WPRS Multiphysics EGTHM Reactor physics Multiphysics EGMUP Reactor physics NSC EGPRS Nuclear science …
    Published date: 18 November 2021
    NEA Document
    Benchmark Specifications for the Fluoride-salt High-temperature Reactor (FHR) Reactor Physics Calculations
    NEA/NSC/R(2020)5

    This benchmark focuses on FHR reactors with plates and triso fuel. Several phases are planned, starting with neutronics on a simple fuel element simulation without burn-up, and gradually extending to...

    Reactor physics Nuclear science EGPRS Verification WPRS Nuclear science Reactor physics …
    Published date: 4 June 2021
    NEA Document
    NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume III: Results of Phase I on Void Distribution
    NEA/NSC/R(2020)6

    In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...

    English Boiling water reactors Nuclear science Nuclear safety WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
    Published date: 1 June 2021
    NEA Document
    NUPEC BWR Full-size Fine-mesh Bundle Test BFBT Benchmark - Volume IV: Results of Phase II on Pressure Drop and Critical Power
    NEA/NSC/R(2020)7

    In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...

    English Boiling water reactors Nuclear science Nuclear safety WPRS EGTHM Reactor physics Reactor physics Nuclear science Benchmark …
    Published date: 2 December 2021
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 1 Phase I (V1000CT-1), Volume 3: Summary Results of Exercise 2 on Coupled 3-D Kinetics/Core Thermal-hydraulics

    In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

    English Reactor physics Nuclear science WPRS Multiphysics Nuclear science Reactor physics Multiphysics EGMUP …
    Published date: 16 November 2007
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 2 (V1000CT-2): Summary Results of Exercise 1 on Vessel Mixing Simulation

    Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...

    English Reactor physics Nuclear science WPRS Multiphysics Nuclear science Reactor physics Multiphysics EGMUP …
    Published date: 5 October 2010
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