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    Event
    20th Meeting of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)
    20 - 24 February 2023
    Paris, OECD NEA

    Under the guidance of the  Nuclear Science Committee (NSC) , the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, ...

    Nuclear science WPRS Multiphysics Radiation transport and shielding Thermal hydraulics and mechanics Reactor physics …
    Published date: 31 March 2022
    Event
    SATIF-15: 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF)
    20 - 23 September 2022
    Facility for Rare Isotope Beams at Michigan State University, East Lansing, Michigan (USA)

    The 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) is tentatively planned to be held in East Lansing, Michigan, USA, on 20-23 September 2022. The SATI...

    Radiation transport and shielding Radiological protection for occupational exposure at nuclear Installations Reactor physics
    Published date: 2 November 2021
    Event
    27th Meeting of the Working Party on Nuclear Criticality Safety (WPNCS)
    27 June 2022 - 1 July 2022
    OECD headquarters, Paris XVI

    Under the guidance of the  Nuclear Science Committee (NSC) , the Working Party on Nuclear Criticality Safety (WPNCS) focuses on technical and scientific issues related to criticality safety. Specific...

    Criticality safety Nuclear science Criticality WPNCS
    Published date: 17 May 2022
    Event
    WPRS Benchmark Workshop 2022
    30 May 2022 - 3 June 2022
    Conference Center Hotel Aquabella, Aix-en-Provence, France (in-person meeting)

    The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted by CEA Cadarache in Aix-en-Provence. During the week of 30 May to 3 ...

    Thermal hydraulics and mechanics Reactor physics Reactor fuel performance
    Published date: 29 March 2022
    News
    Joint Evaluated Fission and Fusion (JEFF) Nuclear Data Week 2022

    The NEA Data Bank Nuclear Data Service (NDS) organised the Joint Evaluated Fission and Fusion (JEFF) Nuclear Data Week (NDW) on 25-29 April 2022.

    News brief Nuclear data Data Bank
    Published date: 20 May 2022
    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
    Published date: 17 May 2022
    Activity
    Nuclear Data Sensitivity Tool (NDaST)

     Nuclear Data Sensitivity Tool (NDaST), aims to provide rapid feedback on the effect of changes to nuclear data on integral benchmarks.

    Nuclear science Verification and validation Nuclear data Databases
    Published date: 17 May 2022
    News
    Momentum building in the Framework for Irradiation Experiments

    Recent meetings of groups working under the aegis of the Framework for Irradiation Experiments (FIDES) have demonstrated that the international community is enthusiastic and on a strong course to ful...

    Nuclear fuel News brief Nuclear science Materials science Experimental needs …
    Published date: 5 May 2022
    Activity
    McMaster Core Thermal-Hydraulics Benchmark

    Building on the OECD-NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group...

    Nuclear science Thermal hydraulics Verification and validation Validation Benchmark Reactor physics …
    Published date: 29 April 2022
    Activity
    Database for ICSBEP (DICE)

    The International Criticality Safety Benchmark Evaluation Project (ICSBEP) released the first version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experime...

    Criticality safety Information, data and knowledge management Databases Benchmark
    Published date: 25 April 2022
    Activity
    IRPhE primary documentation

    Collected sources of primary documentation for reactor physics benchmarks.

    Modelling and simulation Reactor physics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 14 April 2022
    Activity
    Liquid Metal Fast Reactor Core Thermal-Hydraulics Benchmark (LMFR T/H)

    The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests ...

    Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 12 April 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
    Activity
    Lead Fast Reactor Benchmark (LFR)

    Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...

    Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 31 March 2022
    Activity
    Expert Group on Physics of Reactor Systems (EGPRS)

    Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) performs specific tasks associa...

    Reactor physics Molten salt reactors Light water reactors Pressurised heavy water reactors Reactor physics …
    Published date: 29 March 2022
    Activity
    Pellet-Cladding Mechanical Interaction (PCMI) Benchmark

    The aim of the benchmark is to improve understanding and modelling of pellet-cladding mechanical interaction (PCMI) amongst NEA member organisations. This is achieved by comparing PCMI predictions of...

    Nuclear fuel Reactor physics Light water reactors EGRFP Benchmark Reactor physics …
    Published date: 23 March 2022
    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: 23 March 2022
    Activity
    Multi-physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) Benchmark

    Multi-physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) Benchmark

    Multi-physics simulations Nuclear science Multiphysics Benchmark
    Published date: 23 March 2022
    Activity
    International Reactor Physics Handbook Database and Analysis Tool (IDAT)

    The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the IRPhE Handbook DVD. This database and corresponding user interface allows easy access to handbook inform...

    Verification and validation Information, data and knowledge management Databases Reactor physics
    Published date: 17 March 2022
    Event
    16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT)

    The NEA is organising the 16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT).

    Advanced nuclear fuel cycles to improve the safety, sustainabilit...

    Nuclear fuel WPFC Fission products Chemistry Actinides Advanced reactors Minor actinides Back-end Nuclear fuel cycle Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 17 March 2022
    Activity
    Shielding Integral Benchmark Archive and Database (SINBAD)

    The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.

    Transport Experiments Radiation Validation Databases Benchmark Radiation transport and shielding Reactor physics …
    Published date: 10 March 2022
    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 NSC Nuclear science Liquid metal reactors Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 24 February 2022
    Activity
    WPFC Expert Group on Fuel Recycling and Waste Technology (EGFRW)

    Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Fuel Recycling and Waste Technology (EGFRW) focuses on the separation processes releva...

    Nuclear fuel WPFC EGFRC Fuel studies NSC Nuclear science Partitioning and transmutation EGFRW Fuel cycle physics and chemistry …
    Published date: 23 February 2022
    Event
    19th Meeting of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)
    21 - 25 February 2022
    ZOOM virtual meeting

    Under the guidance of the  Nuclear Science Committee (NSC) , the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, ...

    Nuclear science Multiphysics Radiation transport and shielding Thermal hydraulics and mechanics Reactor physics …
    Published date: 7 February 2022
    Activity
    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) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...

    Nuclear fuel Reactor physics Multi-physics simulations Fuel studies Light water reactors Thermal hydraulics WPRS Pressurised heavy water reactors Reactor physics Multiphysics …
    Published date: 18 February 2022
    News
    Addressing technical and scientific issues around nuclear criticality safety

    WPNCS bi-annual event brought together 80 experts from 17 member countries.

    News brief Criticality safety Criticality WPNCS
    Published date: 7 February 2022
    Activity
    Expert Group on Reactor Systems Multi-Physics (EGMUP)

    The Expert Group on Reactor Systems Multi-Physics (EGMUP) advances the state of the art in establishing processes and procedures for certifying experimental data and benchmarking multi-physics multi-...

    Multi-physics simulations Reactor physics
    Published date: 7 February 2022
    NEA Document
    Subgroup 27: Prompt Photon Production from Fission Products
    NEA/NSC/R(2020)8

    The following report is issued by the WPEC Subgroup 27, which builds upon the work of the previous Subgroups 21 and 23, critically reviewing the gamma emission data and providing recommendations to i...

    WPEC Fission products Nuclear data
    Published date: 1 February 2022
    Publications and Reports
    The Strategic Plan of the Nuclear Energy Agency 2023-2028

    The OECD Nuclear Energy Agency (NEA) Strategic Plan serves as a guiding instrument that reflects the priorities of its member countries as the Agency addresses evolving needs in the exploration and a...

    English Nuclear law Human aspects of nuclear safety Nuclear law Radiological protection Nuclear science Nuclear safety Nuclear economics Nuclear technology Decommissioning and legacy management Nuclear decommissioning Radioactive waste management Nuclear safety research Safety Data Bank Nuclear safety regulation Nuclear economics …
    Published date: 25 January 2022
    Activity
    Burn-up credit criticality safety

    Burn-up credit is a safety approach that accounts for the reduction in the reactivity of configurations with spent nuclear fuel due to the change in their composition after irradiation.

    Criticality safety NSC Nuclear science Criticality WPNCS …
    Published date: 21 January 2022
    Activity
    Expert Group on Reactor Core Thermal-Hydraulics and Mechanics (EGTHM)

    Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...

    Reactor physics Sodium-cooled reactor Molten salt reactors Light water reactors Thermal hydraulics WPRS Reactor physics …
    Published date: 22 December 2021
    Activity
    Workshops on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF)

    The mission of the Expert Group of Shielding aspects of Accelerators, Targets and Irradiation Facilities (SATIF) has been completed. Its work initiated the SATIF workshops which keep on serving as in...

    Radiation transport and shielding
    Published date: 16 December 2021
    News
    Recent webinar highlights Italy’s role in nuclear science and technology

    The webinar "Research and international dialogue in technology nuclear power - What role for Italy?", was held on 17- 18 November 2021.

    Nuclear science Italy
    Published date: 14 December 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 Reactor physics Boiling water reactors Nuclear safety Benchmark Reactor physics …
    Published date: 2 December 2021
    Activity
    Expert Group on Multi-physics Experimental Data, Benchmarks and Validation (EGMPEBV)

    The expert group dealt with the activities associated with the certification of experimental data and benchmark models along with establishing the processes and procedures for using the data and benc...

    Multi-physics simulations NSC Nuclear science Verification and validation Validation Information, data and knowledge management Nuclear data Benchmark Multiphysics …
    Published date: 23 November 2021
    Activity
    Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF)

    The Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF) dealt with the various aspects of the modelling and design of accelerator shield systems and radiatio...

    Reactor physics Nuclear science Radiation shielding Radiation transport and shielding Reactor physics …
    Published date: 19 November 2021
    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: 10 November 2021
    News
    High entropy alloys for advanced nuclear applications

    The NEA Expert Group on Innovative Structural Materials (EGISM) organised a workshop on 19-21 October 2021 together with the Spanish Center for Energy, Environmental and Technological Research (CIEMA...

    Material science News brief Nuclear science Materials science EGISM Fuel cycle physics and chemistry …
    Published date: 3 November 2021
    Activity
    Expert Group on Uncertainty Analysis in Modelling (EGUAM)

    The expert group provided advice to the Working Party on Scientific Issues of Reactor Systems (WPRS) on the scientific development needs (data and methods, validation experiments, scenario studies) o...

    EGUAM Boiling water reactors Nuclear science Light water reactors WPRS Reactor physics Modelling and simulation Reactor physics Uncertainty quantification Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 27 October 2021
    News
    International review of benchmark experiments

    ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings, October 2021.

    News brief Criticality safety Nuclear science ICSBEP IRPhEP Reactor physics …
    Published date: 25 October 2021
    Activity
    WPFC Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS)

    Under the guidance of the  Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) , the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS) studies the needs associated with the transit...

    Nuclear fuel WPFC Fuel studies NSC Nuclear science EGAFCS Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 15 October 2021
    Activity
    WPFC Expert Group on Reactor Coolants/Components Technology (EGCoCoT)

    Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Reactor Coolants and Components Technology (EGCoCoT) undertakes activities with the go...

    Nuclear fuel WPFC EGLM Fuel studies NSC Nuclear science EGCoCoT Liquid metal reactors Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 15 October 2021
    Activity
    WPFC Expert Group on Innovative Fuel Elements (EGIFE)

    Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Innovative Fuel Elements (EGIFE) conducts joint and comparative studies to identify te...

    Nuclear fuel WPFC Fuel studies NSC EGIFE Nuclear science EGIF Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 15 October 2021
    Activity
    Benchmark of the Modular High-Temperature Gas-Cooled Reactor-350 MW Core Design

    Helium-cooled very high-temperature gas reactors are highlighted as a key technology with the potential to improve the competitiveness of nuclear energy within the Generation IV International Forum (...

    Gas-cooled reactors Reactor physics
    Published date: 20 September 2021
    Activity
    Physics of plutonium recycling

    For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.

    Reactor physics Plutonium Nuclear fuel cycle Reactor physics
    Published date: 8 September 2021
    Activity
    Nuclear Education, Skills and Technology (NEST) Framework

    The NEA launched the Nuclear Education, Skills and Technology (NEST) Framework in partnership with its member countries to help address important gaps in nuclear skills capacity building, knowledge t...

    Nuclear science Education Nuclear Education, Skills and Technology (NEST) Framework Human resources development (HRD) International co-operation Training Nuclear knowledge management …
    Published date: 7 September 2021
    Activity
    Neutron noise analysis

    Neutron noise analysis can be defined as the direct measurement of the kinetics of a nuclear core. This page describes some of the NEA's previous activities on neutron noise analysis in nuclear power...

    Nuclear science Fast reactor Benchmark Reactor physics
    Published date: 26 July 2021
    Activity
    VVER-1000 Coolant Transient (V1000CT) Benchmarks

    The overall objective of the VVER-1000 Coolant Transient (V1000CT) Benchmark was to assess computer codes used in the safety analysis of water-water energetic reactor (VVER) power plants, specificall...

    Verification Multiphysics Benchmark Reactor physics Pressurised water reactors …
    Published date: 26 July 2021
    Activity
    Pressurised Water Reactor Main Steam-Line Break (MSLB) Benchmark

    This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

    Modelling and simulation Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics …
    Published date: 26 July 2021
    Activity
    Benchmark Based on NUPEC Pressurised Water Reactor (PWR) Subchannel and Bundle Tests (PSBT)

    An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.

    Reactor physics Nuclear science Thermal hydraulics Multiphysics Benchmark Reactor physics Pressurised water reactors Multiphysics …
    Published date: 26 July 2021
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