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    News
    Progress in advanced fuel cycles and partitioning and transmutation

    The NEA hosted the 16th edition of information exchange meetings on actinide and fission product partitioning and transmutation (16IEMPT).

    Nuclear fuel WPFC News brief Fission products Actinides Nuclear science Nuclear fuel cycle Partitioning and transmutation Minor actinides …
    Published date: 22 November 2023
    Event
    21st Meeting of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)
    19 - 23 February 2024
    NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France), remote access only under exceptional circumstances

    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, an...

    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: 29 November 2023
    News
    First international benchmark of artificial intelligence and machine learning in nuclear reactor physics

    The benchmark will predict the Critical Heat Flux (CHF).

    News brief Nuclear science WPRS Thermal hydraulics and mechanics Reactor physics Reactor fuel performance Multiphysics EGMUP Reactor physics Nuclear science Benchmark …
    Published date: 22 November 2023
    News
    NEA Data Bank training: Introduction to FLUKA.CERN and SERPENT-2

    In November 2023, the NEA Data Bank held two beginner level courses in Paris, France.

    News brief Nuclear science CPS Education Nuclear data Data Bank Training …
    Published date: 21 November 2023
    News
    Members of NEA Second Framework for Irradiation Experiments (FIDES-II) meet in Japan

    FIDES-II member assembled at the Japan Atomic Energy Agency (JAEA) in Mito, Japan.

    Fuel in nuclear safety Nuclear fuel News brief Nuclear science FIDES Nuclear safety research Joint project Reactor fuel performance Nuclear science Accident Tolerant Fuels …
    Published date: 23 November 2023
    News
    Addressing challenges of chemical processes and technologies in molten salt reactor fuel cycles

    The NEA and IAEA jointly organised an international workshop in Vienna, Austria, on 2-6 October 2023.

    News brief Nuclear science Molten salt reactors Nuclear science Nuclear fuel cycle EGFRW Fuel cycle physics and chemistry …
    Published date: 21 November 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 institutions ...

    Fuel in nuclear safety Nuclear fuel Nuclear science FIDES Nuclear safety research Accident tolerant fuels Reactor fuel performance …
    Published date: 21 November 2023
    Event
    Materials Modelling and Simulation for Nuclear Fuel (MMSNF) Workshop 2023
    28 - 30 November 2023
    McMaster University, Hamilton, ON (Canada)

    The Materials Modelling and Simulation for Nuclear Fuels (MMSNF) Workshop is a forum for the discussion of state-of-the-art modelling and simulation techniques for nuclear fuels and cladding material...

    Material science Nuclear science Materials science WPFM Nuclear science …
    Published date: 20 November 2023
    Activity
    WPFC Task Force on Benchmarking of Thermal-Hydraulic Loop Models for Lead Alloy-Cooled Advanced Nuclear Energy Systems (LACANES)

    The task force developed best practice guidelines by performing a benchmark study on thermo-hydraulic modelling of heavy liquid metal coolant, e.g. lead and lead-bismuth eutectic (LBE) alloy.

    Nuclear fuel WPFC EGLM Fuel studies NSC Nuclear science Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 28 February 2020
    Activity
    WPFC Expert Group on Heavy Liquid Metal (EGHLM) Technology

    The expert group monitored the feedback from version 0 of the Lead-bismuth eutectic (LBE) handbook, collected, analysed and checked the consistency of expected new results from ongoing heavy liquid m...

    Nuclear fuel WPFC EGLM Fuel studies NSC Nuclear science Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 28 February 2020
    Event
    Meetings of the ICSBEP and IRPhE Technical Review Groups and the SINBAD Task Force
    15 - 19 April 2024
    Lawrence Livermore National Laboratory (LLNL), California, USA

    The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiments Evaluation Project (IRPhEP) Technical Review Groups, and the Shielding Int...

    Nuclear science ICSBEP WPRS Radiation transport and shielding IRPhEP Reactor physics Criticality safety NSC Verification and validation SINBAD Nuclear science Benchmark …
    Published date: 17 November 2023
    Joint project
    Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression (TCOFF)

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

    TCOFF Phases

    First Phase (2017-2020)

    The Thermodynamic Characterisation of Fuel Debris and Fission Products ...

    Nuclear science Fission products Fukushima Thermodynamic data Nuclear safety research Safety research …
    Published date: 6 October 2023
    Activity
    SINBAD - Shielding Integral Benchmark Archive and Database

    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 Databases Radiation transport and shielding Reactor physics Integral experiments Verification and validation Validation SINBAD Benchmark …
    Published date: 14 November 2023
    NEA Document
    The Effect of Temperature on the Neutron Multiplication Factor for Pressurised Water Reactor Fuel Assemblies: A Temperature Analysis Benchmark
    NEA/NSC/R(2022)1

    There is significant international interest in the effects of temperature on criticality safety evaluations. Improved access to nuclear data, notably thermal scattering data S(α,β) for hydrogen in ic...

    Nuclear science WPNCS Benchmark Pressurised water reactors
    Published date: 2 November 2023
    Activity
    Neutronics/Thermal-hydraulics Coupling in Light Water Reactor (LWR) Technology (CRISSUE-S)

    The CRISSUE-S Project was created to re-evaluate fundamental technical issues with the technology of light water reactors (LWRs).

    Nuclear science Light water reactors
    Published date: 2 November 2023
    Event
    NEA Global Forum on Nuclear Education, Science, Technology and Policy: Country-specific Workshop in the Republic of Korea
    17 - 18 October 2023
    Seoul, Korea

    Encouraging greater cohesion of social sciences and STEM to push the nuclear sector forward

    The NEA Global Forum on Nuclear Education, Science Technology and Policy (the NEA Global Forum) held a coun...

    Nuclear science Education Human resources development (HRD) Capacity building and gender Global Forum Nuclear science Training Nuclear knowledge management Korea …
    Published date: 27 September 2023
    News
    Data preservation and fuel safety criteria in focus at annual WGFS meeting

    Experts from 16 countries met on 13-15 September for the 24th annual Working Group on Fuel Safety GFS meeting in Paris. 

    Fuel in nuclear safety Nuclear fuel News brief Fuel studies Member countries Reactor fuel performance Nuclear fuel cycle WGFS Fuel cycle physics and chemistry …
    Published date: 27 October 2023
    Activity
    IRPhE Technical Review Group

    The International Reactor Physics Experiment Evaluation (IRPhE) Technical Review Group provides the nuclear community with qualified benchmark data sets by collecting reactor physics experimental dat...

    Modelling and simulation Reactor physics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 10 November 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: 17 May 2023
    Event
    16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT)
    24 - 27 October 2023
    NEA Headquarters, Boulogne-Billancourt, France

    The NEA is organising the 16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT) on 24-27 October 2023. The meeting will be held at the NEA offices...

    Nuclear fuel WPFC Fission products Chemistry Actinides Advanced reactors Minor actinides NSC Back-end Nuclear fuel cycle Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 23 October 2023
    Event
    International Conference on Nuclear Criticality Safety (ICNC) 2023
    1 - 6 October 2023
    Sendai International Center, Miyagi, Japan

    The 12th International Conference on Nuclear Criticality Safety (ICNC) was held in Sendai, Japan, on 1-6 October 2023. Twenty years after the last conference in Japan, which was held in Tokai-mura as...

    Criticality safety WPNCS Safety Co-sponsored event
    Published date: 13 December 2022
    Event
    Benchmarking Artificial Intelligence and Machine Learning for Criticial Heat Flux Predictions
    30 October 2023
    13:00-15:00 CET, Online

    Recent performance breakthroughs in Artificial Intelligence (AI) and Machine Learning (ML) have led to unprecedented interest in AI/ML among nuclear engineers. However, the lack of dedicated benchmar...

    Nuclear science WPRS Multiphysics Nuclear science Reactor physics EGMUP …
    Published date: 4 October 2023
    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: 4 October 2023
    Activity
    Task Force on Artificial Intelligence and Machine Learning for Scientific Computing in Nuclear Engineering

    The EGMUP Task Force on artificial intelligence and machine learning will design benchmark specifications to evaluate the performance of AI/ML in multi-physics modeling and simulation of reactor syst...

    Multiphysics Thermal hydraulics and mechanics Reactor physics Reactor fuel performance
    Published date: 4 October 2023
    Activity
    NEA Global Forum on Nuclear Education, Science, Technology and Policy

    The Global Forum on Nuclear Education, Science, Technology and Policy acts as an inclusive network of experts in the nuclear energy sector, primarily from academia, focused on enabling the generation...

    Nuclear science Education Human resources development (HRD) International co-operation Training Nuclear knowledge management …
    Published date: 2 October 2023
    Publications and Reports
    Specifications for the Generalised Nuclear Database Structure Version 2.0

    Knowledge of basic nuclear physics data is essential for the modelling and safe operation of all types of nuclear facilities. The de facto international standard format, Evaluated Nuclear Data File 6...

    English WPEC Nuclear science Nuclear science Nuclear data processing …
    Published date: 22 September 2023
    NEA Document
    Benchmark on Dose Rate Calculations for Irradiated Assembly
    NEA/NSC/R(2023)8

    The Task Force on Dose Rate Calculations for Irradiated Fuel Assembly was launched in 2015 to assess code predictions of dose rates from bare spent fuel assemblies and to benchmark multiple codes and...

    WPFC Nuclear science Spent fuel Nuclear science Benchmark …
    Published date: 19 September 2023
    NEA Document
    Experimental Needs for Criticality Safety Purposes
    NEA/NSC/R(2022)6

    The goal of the Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) Subgroup on Experimental Needs for Criticality Safety Purposes (SG-5) was to highlight the needs of int...

    Criticality safety Nuclear science Criticality WPNCS Experimental needs Nuclear science …
    Published date: 15 September 2023
    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: 13 September 2023
    Activity
    Burn-up credit and nuclear 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: 11 September 2023
    Event
    TCOFF-II call for R&D proposals
    6 September 2023 - 27 October 2023

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

    Nuclear science Thermodynamics Thermodynamic data TCOFF Nuclear science Joint project …
    Published date: 5 September 2023
    NEA Document
    Burnup Credit Criticality Benchmark Phase IIID: Burnup Calculations of Gadolinium- Bearing Fuel Rods in Boiling Water Reactor Assemblies for Storage and Transportation
    NEA/NSC/R(2022)3/CORR

    Please note that this report was initially published in November 2022 (NEA/NSC/R(2022)3) under erroneous benchmark number IIB; in this updated version (NEA/NSC/R(2022)3/CORR) this has been corrected ...

    Criticality safety Nuclear science WPNCS Nuclear science Benchmark …
    Published date: 30 November 2022
    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 organised 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) Unce...

    Nuclear science Education WPRS Nuclear science Reactor physics …
    Published date: 4 May 2023
    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: 28 August 2023
    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 transitio...

    Nuclear fuel WPFC Fuel studies NSC Nuclear science EGAFCS Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 28 August 2023
    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: 28 August 2023
    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 to collect,...

    Nuclear fuel WPFC EGLM Fuel studies NSC Nuclear science EGCoCoT Liquid metal reactors Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 28 August 2023
    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: 28 August 2023
    Activity
    Working Party on International Nuclear Data Evaluation Co-operation (WPEC)

    The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countrie...

    NSC Nuclear science Nuclear data
    Published date: 28 August 2023
    Joint project
    Thermodynamics of Advanced Fuels - International Database (TAF-ID)

    On this page

    • TAF-ID Project
    • TAF-ID database: working and public versions
    • Goals of the TAF-ID project phases
    • Why is thermodynamic data for analyses involving nuclear fuel needed?
    • How is thermodynami...
    Material science Structural materials Fuel studies Nuclear science Materials science Thermodynamic data TAF-ID …
    Published date: 2 August 2023
    News
    The demise of zero power reactors: Addressing reduced experimental capabilities

    The NEA workshop gathered experts to discuss the challenges and opportunities related to the demise of zero power reactors.

    NSC Nuclear science WPRS Nuclear science
    Published date: 4 July 2023
    News
    Experts gather to discuss nuclear criticality safety

    The NEA Working Party on Nuclear Criticality Safety (WPNCS) held its bi-annual meetings in June 2023

    News brief Criticality safety Fuel studies Nuclear science Criticality WPNCS Benchmark …
    Published date: 24 July 2023
    News
    Training FISPACT-II users

    Co-organised with the UK Atomic Energy Authority, the course took place on 20-22 June 2023.

    News brief Nuclear science CPS Data Bank Nuclear science Training Codes and programs …
    Published date: 24 July 2023
    Activity
    Thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H)

    High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...

    Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 19 July 2023
    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 July 2023
    Event
    Sixteenth Workshop on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-16)
    28 - 31 May 2024
    INFN Laboratori Nazionali di Frascati, Frascati, Italy

    The Sixteenth Workshop on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-16) will take place on 28-31 May 2024 at the National Laboratories of Frascati of the Italian Na...

    Radiation shielding Nuclear science Radiation transport and shielding Co-sponsored event
    Published date: 18 July 2023
    News
    Improving thermodynamic databases and materials modelling for the analysis of severe accidents

    TCOFF-2 members discuss future activities.

    Thermodynamic data TCOFF Nuclear science Joint project Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 10 July 2023
    Event
    The demise of zero power reactors: From concern to action
    22 - 23 June 2023
    IRSN, Fontenay-aux-Roses, France

    In the early decades of nuclear reactor development, many countries built and operated zero-power facilities in which many different critical arrangements of materials were studied. These flexible ex...

    NSC Nuclear science WPRS Nuclear science
    Published date: 6 June 2023
    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
    News
    Benchmarking state-of-the art nuclear reactor simulations

    The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.

    Reactor physics Nuclear science WPRS Multiphysics Nuclear science Benchmark Thermal hydraulics and mechanics Reactor physics Reactor fuel performance Multiphysics …
    Published date: 13 June 2023
    News
    Strategic use of nuclear fuel and materials research facilities – a pioneering output of the FIDES-II Framework

    10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.

    Fuel in nuclear safety Nuclear fuel Nuclear science Nuclear safety FIDES Nuclear safety research Reactor fuel performance Nuclear science Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 19 June 2023
    News
    Challenging state-of-the art thermal hydraulics simulation capabilities for high temperature gas-cooled reactors

    Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.

    News brief Nuclear science WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Thermal hydraulics Nuclear science Benchmark …
    Published date: 16 June 2023
    News
    Training the next generation of nuclear simulation specialists

    The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.

    Reactor physics News brief Nuclear science Education WPRS Nuclear science Reactor physics …
    Published date: 14 June 2023
    News
    Advancing the understanding of materials science issues in nuclear fuels and structural materials

    WPFM held meetings on 23-25 May 2023.

    Material science Modelling and simulation News brief Nuclear science Materials science WPFM Nuclear science …
    Published date: 13 June 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: 13 June 2023
    Activity
    Lead-cooled 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 ...

    Generation IV reactors Verification and validation Verification Validation Liquid metal reactors Benchmark Reactor physics …
    Published date: 9 June 2023
    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: 8 June 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: 1 June 2023
    Subtopic
    Education and capacity building

    Sustained performance of nuclear technology depends on access to a talented and well-qualified workforce, thus it is important to ensure that adequate infrastructures exist for education and training...

    Nuclear science Education Training
    Published date: 22 July 2020
    Activity
    Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM)

    The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....

    Sodium-cooled reactor Verification Fast reactor Benchmark Reactor physics …
    Published date: 24 May 2023
    Event
    WPRS Benchmarks Workshop 2023
    22 - 26 May 2023
    Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy + virtual option on ZOOM

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

    Reactor physics Nuclear science Multiphysics Nuclear science Benchmark Thermal hydraulics and mechanics Reactor physics Reactor fuel performance Multiphysics …
    Published date: 17 May 2023
    Activity
    Nuclear Science Committee (NSC)

    The NEA nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.

    Nuclear fuel Reactor physics Nuclear science Criticality Materials science Chemistry …
    Published date: 15 May 2023
    NEA Document
    Benchmark Study on Innovative Fuels for Fast Reactors with Fuel Performance Codes
    NEA/NSC/R(2022)5

    This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...

    WPFC Fuel studies NSC Nuclear science Nuclear science Benchmark Reactor fuel performance Fuel cycle physics and chemistry …
    Published date: 3 April 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 NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 17 February 2023
    NEA Document
    Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors: Volume I. Neutronics Phase (Phase I)
    NEA/NSC/R(2021)5

    Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...

    Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Benchmark …
    Published date: 18 April 2023
    Event
    International workshop on thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H)
    5 - 6 June 2023
    Oregon State University, Corvallis, Oregon, United States

    The NEA thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H), supervised by the Expert Group on Reactor Core Thermal-Hydraulics and Mechanic...

    Nuclear science Thermal hydraulics and mechanics Reactor physics Reactor physics NSC Thermal hydraulics Verification and validation Verification Validation Benchmark …
    Published date: 20 April 2023
    News
    ICSBEP and IRPhEP Technical Review Group meetings

    The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.

    News brief Nuclear science Criticality ICSBEP IRPhEP Reactor physics Reactor physics Criticality safety NSC SINBAD Nuclear science Benchmark …
    Published date: 24 April 2023
    News
    Members of NEA Second Framework for Irradiation Experiments (FIDES-II) meet in Czech Republic

    Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.

    Fuel in nuclear safety Nuclear fuel News brief Nuclear science Nuclear safety FIDES Reactor fuel performance NSC Nuclear science Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 21 April 2023
    News
    Discussing scientific issues in the design and qualification of reactor systems

    The WPRS met from 20-24 February 2023.

    News brief NSC Nuclear science SINBAD WPRS Multiphysics Nuclear science Benchmark Multiphysics …
    Published date: 17 March 2023
    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

    News brief Fuel studies Nuclear science Materials science Databases Material science NSC WPFM 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 NSC Thermodynamic data TCOFF …
    Published date: 24 February 2023
    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 NSC Thermodynamic data TAF-ID …
    Published date: 24 February 2023
    Activity
    Nuclear Science Committee Programme Review Group (NSC PRG)

    Established to help fulfil the objectives of the Agency and the Nuclear Science Committee (NSC), the NSC Programme Review Group (PRG) formulates recommendations based on best practices to optimise ac...

    NSC Nuclear science Nuclear science
    Published date: 4 May 2023
    Activity
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM)

    The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...

    Modelling and simulation Reactor physics Light water reactors Verification and validation Validation Uncertainty quantification Uncertainty analysis Benchmark Reactor physics Pressurised water reactors …
    Published date: 25 April 2023
    Activity
    International Fuel Performance Experiments (IFPE) database

    International Fuel Performance Experiments (IFPE) is a data collection of nuclear fuel performance experiments for the purpose of code development and validation.

    Fuel studies Nuclear science Experiments EGRPF Databases Ancillary data Reactor physics …
    Published date: 19 April 2023
    Activity
    DATabase for IFpe (DATIF)

    Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...

    Nuclear fuel Physics Fuel studies NSC EGRFP Databases Ancillary data Reactor physics Integral experiments …
    Published date: 12 April 2023
    News
    ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings

    ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings

    News brief Criticality safety Nuclear science SINBAD Reactor physics …
    Published date: 18 November 2019
    News
    Scientific issues of nuclear reactor systems

    NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.

    Reactor physics News brief Nuclear science SINBAD Reactor physics …
    Published date: 4 March 2020
    News
    International review of benchmark experiments

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

    News brief Criticality safety Nuclear science SINBAD ICSBEP IRPhEP Reactor physics …
    Published date: 25 October 2021
    News
    Scientific issues and uncertainty analysis of nuclear reactor systems

    NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 2021.

    Reactor physics News brief Nuclear science EGPRS SINBAD WPRS Reactor physics …
    Published date: 24 February 2021
    News
    Enhancing the NEA Shielding Integral Benchmark Archive and Database (SINBAD)

    EGPRS Task Force members met on 3 April 2023.

    Reactor physics News brief NSC Nuclear science Radiation shielding EGPRS SINBAD WPRS Reactor physics …
    Published date: 7 April 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
    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
    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
    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
    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
    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
    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
    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
    NEA Document
    PBMR Coupled Neutronics/Thermal-Hydraulics Transient Benchmark: The PBMR-400 Core Design - Volume 1: The Benchmark Definition
    NEA/NSC/DOC(2013)10

    This report defines the “OECD/NEA/NSC PBMR Coupled Neutronics/Thermal-hydraulics Transient Benchmark of the PBMR-400 Core Design”. This chapter gives more information on the day-to-day management of ...

    English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics Reactor physics Multiphysics EGMUP Modelling and simulation Reactor physics NSC Thermal hydraulics Nuclear science Benchmark …
    Published date: 19 June 2013
    NEA Document
    OECD/NRC Benchmark Based on NUPEC Pressurised Water Reactor Sub-channel and Bundle Tests (PSBT) - Volume I: Experimental database and final problem specifications
    NEA/NSC/DOC(2012)1

    Based on the success of the OECD/NRC BFBT Benchmark, Japan released data based on the NUPEC PWR Sub-channel and Bundle Tests (PSBT) Benchmark and asked Pennsylvania State University (PSU) in the Unit...

    English Nuclear science WPRS Multiphysics EGTHM Reactor physics Multiphysics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
    Published date: 4 January 2012
    NEA Document
    Benchmarks for Uncertainty Analysis in Modelling (UAM) for the Design, Operation and Safety Analysis of LWRs - Volume I: Specification and Support Data for Neutronics Cases (Phase I)
    NEA/NSC/DOC(2013)7
    English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
    Published date: 16 May 2013
    Publications and Reports
    NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark - Volume II: Uncertainty and Sensitivity Analyses of Void Distribution and Critical Power - Specification

    This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared j...

    English Nuclear science Light water reactors WPRS Thermal hydraulics and mechanics EGTHM Reactor physics Modelling and simulation Reactor physics Verification and validation Validation Uncertainty analysis Nuclear science Benchmark …
    Published date: 1 January 2010
    NEA Document
    Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-14)
    NEA/NSC/R(2021)2

    Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.

    English Nuclear science Radiation shielding WPRS Proceedings Reactor physics Reactor physics NSC EGPRS Nuclear science …
    Published date: 16 December 2021
    NEA Document
    Shielding Aspects of Accelerators, Target and Irradiation Facilities (SATIF-13) - Proceedings of the Thirteenth Meeting, 10-12 October 2016, Dresden, Germany
    NEA/NSC/R(2018)2
    English Reactor physics NSC Nuclear science Radiation shielding EGPRS WPRS Nuclear science Proceedings Reactor physics …
    Published date: 8 December 2021
    NEA Document
    Shielding Aspects of Accelerators, Target and Irradiation Facilities (SATIF-12)
    NEA/NSC/R(2015)3

    Twelfth Workshop Proceedings, Batavia, Illinois, United States, 28-30 April 2014

    English Reactor physics NSC Nuclear science Radiation shielding EGPRS WPRS Nuclear science Proceedings Reactor physics …
    Published date: 2 June 2015
    Publications and Reports
    Review of Integral Experiments for Minor Actinide Management

    Spent nuclear fuel contains minor actinides (MAs) such as neptunium, americium and curium, which require careful management. This becomes even more important when mixed oxide (MOX) fuel is being used...

    English Reactor physics Nuclear science EGPRS WPRS Nuclear science …
    Published date: 17 February 2015
    Publications and Reports
    NEA brochure

    The brochure provides background information about the NEA.

    English Nuclear law Human aspects of nuclear safety Nuclear law Radiological protection Nuclear science Nuclear economics Nuclear technology Regulation Decommissioning and legacy management Radioactive waste management Nuclear safety research Radiological protection Technology Safety research Radioactive waste management Human action Data Bank Nuclear science Nuclear safety regulation Nuclear economics …
    Published date: 10 September 2018
    NEA Document
    Investigation of Covariance Data in General Purpose Nuclear Data Libraries
    NEA/NSC/R(2021)4

    The understanding of nuclear physics and the associated uncertainties is essential to the modelling of all nuclear systems. Nuclear reaction probabilities, emitted particle energies and angles, fissi...

    WPEC Nuclear science Nuclear data Nuclear science
    Published date: 8 February 2023
    NEA Document
    Role of Integral Experiment Covariance Data for Criticality Safety Validation: EG UACSA Benchmark Phase IV
    NEA/NSC/R(2021)1

    This benchmark report has been compiled under the guidance of the NEA Working Party on Nuclear Criticality Safety (WPNCS) in the Subgroup on the Role of Integral Experiment Uncertainties and Covarian...

    English UACSA Criticality safety Criticality WPNCS Nuclear science Benchmark …
    Published date: 30 January 2023
    NEA Document
    Treatment of Volatile Fission Products
    NEA/NSC/R(2022)4

    Under the auspices of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) was established to co-ordinate scientific activities related to ad...

    Fission products Spent fuel Nuclear science Nuclear fuel cycle EGFRW Fuel cycle physics and chemistry …
    Published date: 29 November 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 science Nuclear safety regulation Nuclear economics …
    Published date: 25 January 2022
    Publications and Reports
    The Strategic Plan of the Nuclear Energy Agency 2017-2022

    This Strategic Plan is intended to guide the NEA as it seeks to meet the evolving needs of member countries in the application and exploration of nuclear science and technology. The plan includes an ...

    English Nuclear law Human aspects of nuclear safety Nuclear law Radiological protection Decommissioning Nuclear science Nuclear economics Nuclear technology Decommissioning and legacy management Nuclear decommissioning Stakeholder Radioactive waste management Nuclear safety research Safety Safety culture Safety research Decontamination Data Bank Nuclear science Nuclear safety regulation Nuclear economics …
    Published date: 22 December 2016
    Publications and Reports
    SATIF-3 - Shielding Aspects of Accelerators, Targets and Irradiation Facilities

    Particle accelerators have evolved over the last 50 years from simple devices to powerful machines, and will continued to have an important impact on research, technology and lifestyle. Today, they c...

    English Nuclear science EGPRS Nuclear science Proceedings …
    Published date: 1 January 1998
    Publications and Reports
    Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF 4

    Over the last 50 years particle accelerators have evolved from simple devices to powerful machines, and will continue to have an important impact on research, technology and lifestyle. Today, they co...

    English Nuclear science EGPRS Nuclear science Proceedings …
    Published date: 1 January 1999
    Publications and Reports
    Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF 5

    Over the last 50 years particle accelerators have evolved from simple devices to powerful machines, and will continue to have an important impact on research, technology and lifestyle. Today, they co...

    English Nuclear science EGPRS Nuclear science Proceedings …
    Published date: 30 May 2001
    Publications and Reports
    Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF 6

    Particle accelerators are used today for an increasing range of scientific and technological applications. They are very powerful tools for investigating the origin and structure of matter, and for i...

    English Nuclear science EGPRS Nuclear science Proceedings …
    Published date: 22 July 2004
    Publications and Reports
    Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF 7

    Particle accelerators are used today for an increasing range of scientific and technological applications. They are very powerful tools to investigate the origin and structure of matter, and to impro...

    English Nuclear science EGPRS Nuclear science Proceedings …
    Published date: 13 May 2005
    Publications and Reports
    Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-10)

    Particle accelerators have evolved over the last decades from simple devices to powerful machines, and are having an increasingly important impact on research, technology and daily life. Today they c...

    English Nuclear science EGPRS Nuclear science Proceedings …
    Published date: 15 December 2010
    Publications and Reports
    Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-11)

    Particle accelerators have evolved over the last decades from simple devices to powerful machines, and are having an increasingly important impact on research, technology and daily life. Today they h...

    English Nuclear science EGPRS Nuclear science Proceedings …
    Published date: 8 October 2013
    NEA Document
    Actinide and Fission Product Partitioning and Transmutation: Workshop Proceedings of the Fifteenth Exchange Meeting Manchester, United Kingdom, 30 September – 3 October 2018
    NEA/NSC/R(2020)4

    Advanced nuclear fuel cycles to improve the safety, sustainability and economics of nuclear energy are being investigated worldwide. Partitioning and transmutation (P&T) is one of the candidate techn...

    Nuclear science Fission products Actinides Nuclear science Nuclear fuel cycle …
    Published date: 11 October 2022
    Publications and Reports
    Nuclear Production of Hydrogen

    Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable source of energy in the 21st century. Present methods for producing hydrogen are mainly based on t...

    English Nuclear science Hydrogen Nuclear science
    Published date: 28 April 2004
    Publications and Reports
    Nuclear Production of Hydrogen

    Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable energy carrier in the 21st century. This report describes the scientific and technical challenges ...

    English Nuclear science Hydrogen Nuclear science
    Published date: 24 June 2010
    Publications and Reports
    Nuclear Production of Hydrogen

    Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable energy carrier in the 21st century. Since natural sources of pure hydrogen are extremely limited, ...

    English Nuclear science Hydrogen Nuclear science
    Published date: 13 July 2006
    Publications and Reports
    Nuclear Production of Hydrogen

    Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable energy source in the 21st century. However, hydrogen does not exist as a gas on earth and thus has...

    English Nuclear science Hydrogen Nuclear science
    Published date: 5 June 2001
    Publications and Reports
    Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation

    One of the important issues regarding deterministic transport methods for whole core calculations is that homogenised techniques can introduce errors into results. On the other hand, with modern comp...

    English Nuclear science Nuclear science
    Published date: 8 August 2003
    NEA Document
    The Effects of the Uncertainty of Input Parameters on Nuclear Fuel Cycle Scenario Studies
    NEA/NSC/R(2016)4
    English Nuclear fuel WPFC Fuel studies NSC Nuclear science Nuclear science EGAFCS Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 10 November 2016
    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 Nuclear science
    Published date: 1 February 2022
    Publications and Reports
    2019 NEA Annual Report

    The NEA Annual Report 2019 provides an overview of the status of nuclear power in NEA member countries and illustrative descriptions of the Agency's activities and international joint projects. 2019 ...

    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 science Nuclear safety regulation …
    Published date: 12 June 2020
    Publications and Reports
    NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark

    Refined models for best-estimate calculations based on good-quality experimental data can improve the understanding of phenomena and the quantification of margins for operating nuclear power reactors...

    English Reactor physics Nuclear science Multiphysics Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 7 July 2006
    NEA Document
    Benchmarking the Accuracy of Solution of 3-Dimensional Transport Codes and Methods over a Range in Parameter Space - Final Meeting held in conjunction with M&C-2009
    NEA/NSC/DOC(2009)8

    Saratoga Springs, New York, 6 May 2009 - Meeting summary

    English Multi-physics simulations NSC Nuclear science Nuclear science Benchmark Multiphysics …
    Published date: 11 May 2009
    NEA Document
    Benchmarking the Accuracy of Solution of 3-Dimensional Transport Codes and Methods over a Range in Parameter Space
    NEA/NSC/DOC(2007)1/1

    Particle transport calculations in three-dimensional configurations are becoming prevalent in nuclear applications. This places a premium on determining the accuracy of numerical solutions to practic...

    English Multi-physics simulations NSC Nuclear science Nuclear science Benchmark Multiphysics …
    Published date: 23 February 2007
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume I

    Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...

    English Nuclear science Nuclear safety research Safety of components and structures Thermal hydraulics and mechanics Modelling and simulation Thermal hydraulics Verification and validation Uncertainty analysis Nuclear science Benchmark Pressurised water reactors …
    Published date: 1 January 1999
    Publications and Reports
    VVER-1000 MOX Core Computational Benchmark

    The United States and the Russian Federation have each agreed to dispose of 34 tonnes of weapons-grade plutonium that are beyond their defence needs. One effective way to dispose of this plutonium is...

    English Modelling and simulation Reactor physics Nuclear science Nuclear science Benchmark Pressurised water reactors …
    Published date: 20 January 2006
    NEA Document
    3-D Radiation Transport Benchmarks for Simple Geometries with Void Region
    NEA/NSC/DOC(2000)4

    Several NEA Nuclear Science Committee (NSC) activities are concerned with the validation of computation methods and codes as applied to nuclear technology. One of the challenges has been and continue...

    English Monte Carlo method Transport NSC Radiation shielding Nuclear science Benchmark Radiation transport and shielding …
    Published date: 17 March 2000
    Publications and Reports
    Very High Burn-ups in Light Water Reactors

    Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...

    English Nuclear fuel Reactor physics Fuel studies Nuclear science Light water reactors Nuclear science Reactor physics …
    Published date: 22 August 2006
    NEA Document
    Overview of SMORN-VI: Summary of the Sixth Symposium on Reactor Noise (SMORN VI)
    NEA/NEACRP/L(1991)333

    A summary of the Sixth Symposium on Reactor Noise (SMORN VI), Gatlinburg, United States, 19-24 May 1991

    English Reactor physics NSC Nuclear science Nuclear science …
    Published date: 1 January 1991
    NEA Document
    VENUS-1 Two-Dimensional Benchmark on Ex-Core Dosimetry Computations
    NEA/NSC/DOC(1996)25

    In this benchmark exercise the goal is to test the current state-of-the-art two-dimensional methods of calculating neutron flux to reactor components against the measured data of the VENUS-1 critical...

    English Reactor physics NSC Nuclear science Nuclear science Benchmark Reactor physics …
    Published date: 1 January 1996
    NEA Document
    Computing Radiation Dose to Reactor Pressure Vessel and Internals: State-of-the-Art Report
    NEA/NSC/DOC(1996)5

    The OECD/NEA Nuclear Science Committee Task Force on Computing Radiation Dose and Modelling of Radiation-induced Degradation of Reactor Components was set up in November 1995 in response to a request...

    English Reactor physics NSC Radiation shielding Radiation Nuclear science Radiation safety Radiation transport and shielding Reactor physics …
    Published date: 1 January 1996
    Publications and Reports
    VENUS-2 MOX-fuelled Reactor Dosimetry Calculations

    It is essential to calculate the structural integrity of reactor components with a high degree of accuracy in order to make correct decisions regarding plant lifetime at the design stage, safety marg...

    English Nuclear science Nuclear science
    Published date: 11 April 2006
    Publications and Reports
    Prediction of Neutron Embrittlement in the Reactor Pressure Vessel

    The OECD/NEA Task Force on Computing Radiation Dose and Modelling of Radiation-Induced Degradation of Reactor Components (TFRDD) launched two international blind intercomparison exercises to examine ...

    English Reactor physics Nuclear science Nuclear science Benchmark Reactor physics …
    Published date: 1 January 2000
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    Physics of Plutonium Recycling - Volume I

    Attitudes towards plutonium management vary from country to country and from utility to utility: some regard plutonium as a liability and others as a valuable source of energy.

    The purpose of this st...

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    Published date: 1 November 1995
    Publications and Reports
    Boiling Water Reactor Turbine Trip (TT) Benchmark - Volume II

    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 Boiling water reactors Nuclear science Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 7 July 2005
    NEA Document
    OECD/NRC Boiling Water Reactor Turbine Trip (TT) Benchmark - Summary of the Third Workshop and Starter Meeting for the VVER-1000 Coolant Transient (V1000-CT) Benchmark
    NEA/NSC/DOC(2002)11

    Rossendorf (Dresden), Germany, 28-30 May 2002

    Reactor physics Boiling water reactors NSC Nuclear science Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 29 July 2002
    NEA Document
    OECD/NRC Boiling Water Reactor Turbine Trip (TT) Benchmark - Summary of the Fourth Workshop
    NEA/NSC/DOC(2002)15

    6 October 2002, Seoul, Korea

    Reactor physics Boiling water reactors NSC Nuclear science Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 1 November 2002
    NEA Document
    OECD/NRC Boiling Water Reactor Turbine Trip (TT) Benchmark - Summary of the Fifth Workshop
    NEA/NSC/DOC(2003)1

    21-22 January 2003, Barcelona, Spain

    Reactor physics Boiling water reactors NSC Nuclear science Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 1 May 2003
    NEA Document
    OECD/NRC Boiling Water Reactor Turbine Trip (TT) Benchmark - Summary of the Second Workshop
    NEA/NSC/DOC(2001)20

    Paul Scherrer Institute, Villigen, Switzerland, 15-16 October 2001

    Reactor physics Boiling water reactors NSC Nuclear science Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 1 October 2001
    NEA Document
    OECD/NRC Boiling Water Reactor Turbine Trip (TT) Benchmark - Summary of the First Workshop
    NEA/NSC/DOC(2000)22
    Reactor physics Boiling water reactors NSC Nuclear science Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 10 December 2000
    Publications and Reports
    Boiling Water Reactor Turbine Trip (TT) Benchmark - Volume I

    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 Boiling water reactors Nuclear science Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 20 July 2001
    Publications and Reports
    Boiling Water Reactor Turbine Trip (TT) Benchmark - Volume IV

    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 Nuclear science Nuclear science
    Published date: 8 October 2010
    Publications and Reports
    Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation

    An important issue regarding deterministic transport methods for whole core calculations is that homogenised techniques can introduce errors into results. In addition, with modern computational abili...

    English Nuclear science Nuclear science
    Published date: 16 September 2005
    Publications and Reports
    Benchmark on the Three-dimensional VENUS-2 MOX Core Measurements

    In order to validate the calculations methods and nuclear data used for the prediction of power in MOX-fuelled systems, the OECD Nuclear Energy Agency (NEA) has examined a series of theoretical physi...

    English Nuclear science Nuclear science
    Published date: 9 February 2004
    NEA Document
    Proceedings of Increased Accident Tolerance of Fuels for Light Water Reactors (2013)
    NEA/NSC/DOC(2013)9

    Workshop Proceedings, 10-12 December 2012

    English Nuclear science EGATFL Nuclear science Proceedings Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 25 February 2020
    NEA Document
    Spent Nuclear Fuel Assay Data for Isotopic Validation - State-of-the-art Report
    NEA/NSC/WPNCS/DOC(2011)5

    Spent Nuclear Fuel Assay Data for Isotopic Validation - State-of-the-art Report

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science ADSNF …
    Published date: 6 June 2011
    Publications and Reports
    NEA News 22.1

    NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...

    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 science Nuclear safety regulation …
    Published date: 29 June 2004
    NEA Document
    Processing Covariance Data for the Resonance Region
    NEA/NSC/R(2020)3

    The following report is issued by WPEC Subgroup 28, which builds upon the work of the previous Subgroup 20 for developing new methods for cross-section covariance evaluation. Subgroup 28 was tasked w...

    NSC Nuclear science Nuclear data Nuclear science
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    Improving Nuclear Data Accuracy of the Am-241 Capture Cross-section
    NEA/NSC/R(2020)2

    The present report provides a summary of the experiments analysed and consensuses reached by NEA WPEC Subgroup 41, including final recommendations based on all experimental data available at the time...

    NSC Nuclear science Nuclear data Nuclear science
    Published date: 28 September 2020
    Publications and Reports
    State-of-the-Art Report on Light Water Reactor Accident-Tolerant Fuels

    As part of a broader spectrum of collaborative activities underpinning nuclear materials research, the Nuclear Energy Agency is supporting worldwide efforts towards the development of advanced materi...

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    Published date: 28 September 2018
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    Curium Management Studies in France, Japan and USA
    NEA/NSC/WPFC/DOC(2012)2
    English Nuclear fuel WPFC United States EGFRC Fuel studies France Nuclear science Japan NSC Nuclear science Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 4 January 2012
    NEA Document
    Spent Nuclear Fuel Reprocessing Flowsheet
    NEA/NSC/WPFC/DOC(2012)15

    Spent Nuclear Fuel Reprocessing Flowsheet

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    Published date: 12 June 2012
    NEA Document
    Benchmark Study on Nuclear Fuel Cycle Transition Scenarios Analysis Codes
    NEA/NSC/WPFC/DOC(2012)16
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    Published date: 12 June 2012
    NEA Document
    Benchmarking of Thermal-Hydraulic Loop Models for Lead-Alloy Cooled Advanced Nuclear Energy Systems – Phase I: Isothermal forced convection case
    NEA/NSC/WPFC/DOC(2012)17

    LACANES – Phase I: Isothermal forced convection case

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    Published date: 12 June 2012
    NEA Document
    Primary Radiation Damage in Materials
    NEA/NSC/DOC(2015)9

    Primary Radiation Damage in Materials – Review of Current Understanding and Proposed New Standard Displacement Damage Model to Incorporate in Cascade Defect Production Efficiency and Mixing Effects

    English Material science WPMM NSC Nuclear science Materials science Nuclear science EGPRD …
    Published date: 26 February 2015
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    State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels
    NEA/NSC/R(2015)5

    State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels

    English WPMM Nuclear science Materials science Material science NSC Nuclear science EGM2F …
    Published date: 3 September 2015
    NEA Document
    Intermediate Report on Methods and Approaches to Provide Feedback from Nuclear and Covariance Data Adjustment for Improvement of Nuclear Data Files
    NEA/NSC/R(2016)6
    English WPEC NSC Nuclear science Nuclear data Nuclear science …
    Published date: 2 December 2016
    NEA Document
    Benchmarking of Thermal-Hydraulic Loop Models for Lead-Alloy-Cooled Advanced Nuclear Energy Systems – Phase II: Natural Convection
    NEA/NSC/R(2018)1

    LACANES – Phase II: Natural Convection

    English WPFC NSC Nuclear science Nuclear science Benchmark Fuel cycle physics and chemistry …
    Published date: 4 April 2018
    Publications and Reports
    Analytical Benchmarks for Nuclear Engineering Applications

    Preservation of know-how in the nuclear field is promoted through the activities of the OECD Nuclear Energy Agency Data Bank. One area of importance concerns methods for solving radiation transport p...

    English Nuclear science Nuclear science
    Published date: 1 September 2008
    Publications and Reports
    State-of-the-art Report on the Progress of Nuclear Fuel Cycle Chemistry

    The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel component...

    English Nuclear fuel WPFC Fuel studies Nuclear science Chemistry Liquid metal reactors NSC Nuclear science Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 19 March 2018
    NEA Document
    Review of Operating and Forthcoming Experimental Facilities Opened to International R&D Co-operation in the Field of Advanced Fuel Cycles
    NEA/NSC/R(2018)4
    English R&D WPFC NSC Chemistry Nuclear science Nuclear fuel cycle Fuel cycle physics and chemistry …
    Published date: 12 December 2018
    NEA Document
    Document content and format guide for the International Criticality Safety Benchmark Evaluation Project (ICSBEP)
    NEA/NSC/DOC(1995)3

    Document content and format guide for the International Criticality Safety Benchmark Evaluation Project (ICSBEP) – NEA/NSC/DOC(95)03

    Criticality safety NSC Nuclear science Criticality WPNCS ICSBEP Nuclear science …
    Published date: 24 March 2020
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase III-A
    NEA/NSC/DOC(1996)4

    Criticality Calculations of BWR Spent Fuel in Storage and Transportation, Yoshitaka Naito, Hiroshi Okuno and Yoshihara Ando (JAERI)

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 1 January 1996
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase IV-A
    NEA/NSC/DOC(2003)3

    Reactivity Prediction Calculations for Infinite Arrays of PWR Mox Fuel Pincells

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 17 April 2003
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase IV-B
    NEA/NSC/DOC(2003)4

    Results and Analysis of MOX Fuels Depletion Calculations

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 17 April 2003
    NEA Document
    Burn-up Credit Benchmark - Phase VIII
    NEA/NSC/R(2016)2

    Numerical benchmark for the analysis of small-sample reactivity experiments

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 9 June 2016
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase I-A
    NEA/NSC/DOC(1993)22

    JAERI-M-94-003 Makoto TAKANO (JAERI), January 1994

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 1 January 1993
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase III-B
    NEA/NSC/DOC(2002)2

    Burn-up Calculations of BWR Fuel Assemblies for Storage and Transport

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 16 January 2002
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase III-A
    NEA/NSC/DOC(2000)12

    Criticality Calculations of BWR Spent Fuel in Storage and Transport, Hiroshi OKUNO, Yoshitaka NAITO, Yoshihira ANDO

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 30 June 2000
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase III-A
    NEA/NSC/DOC(1997)11

    Hiroshi OKUNO, Yoshitaka NAITO and Yoshihira ANDO (JAERI)

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 1 January 1997
    NEA Document
    Burn-up Credit Criticality Benchmark - Part I
    NEA/NEACRP/L(1991)337

    Simple PWR Spent Fuel Cell (Problem Specification), Makoto TAKANO (JAERI), Michaele BRADY (ORNL), 1991

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 1 January 1991
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase II-A
    NEA/NSC/DOC(1993)15

    Effect of Axial Burnup Profile (Infinite fuel pin array) Makoto Takano (JAERI), Michaele Brady (SNL), Alain Santamarina (CEA), June 1993. See NEA/NSC/DOC(96)1

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 1 January 1993
    NEA Document
    Burn-up Credit Criticality Benchmark - Part I-B
    NEA/NSC/DOC(1992)10

    Isotopic Prediction (Problem Specification). Revised, January 1993 Michaele C. Brady<br>See <a href="/html/science/docs/1996/nsc-doc96-06.pdf">NEA/NSC/DOC(96)6</a>.

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 1 January 1992
    NEA Document
    Burn-up Credit Criticality Safety Benchmark - Phase III-C
    NEA/NSC/R(2015)6

    Nuclide Composition and Neutron Multiplication Factor of a Boiling Water Reactor Spent Fuel Assembly for Burn-up Credit and Criticality Control of Damaged Nuclear Fuel

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 2 October 2015
    NEA Document
    Burn-up Credit Criticality Safety Benchmark - Phase II-E
    NEA/NSC/R(2015)1

    Impact of Isotopic Inventory Changes due to Control Rod Insertions on Reactivity and the End Effect in PWR UO2 Fuel Assemblies

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    Published date: 2 June 2015
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase II-B
    NEA/NSC/DOC(1998)1

    Results - Conceptual PWR Spent Fuel Transportation Cask, A. Nouri

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 1 January 1998
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase II-A
    NEA/NSC/DOC(1996)1

    JAERI-Research 96-003, M. Takano, H. Okuno, (JAERI), publication date: February 1996

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 1 January 1996
    NEA Document
    Burn-up Credit Criticality Benchmark - Phase I-B
    NEA/NSC/DOC(1996)6

    Isotopic Prediction: Final Report, M.D. DeHart (ORNL), M.C. Brady (SNL), C.V. Parks (ORNL). Publication date June 1996. ORNL-6901

    English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
    Published date: 1 January 1996
    Publications and Reports
    Source Convergence in Criticality Safety Analyses - Phase I: Results for Four Test Problems

    The NEA Working Party on Nuclear Criticality Safety (WPNCS) established an Expert Group on Source Convergence in Criticality Safety Analysis (EGSCCSA) to explore the problems of slow convergence and ...

    English Nuclear science Nuclear science
    Published date: 11 September 2006
    Publications and Reports
    International Evaluation Co-operation, Volume 13

    Intermediate Energy Data

    English WPEC NSC Nuclear science Nuclear data Nuclear science …
    Published date: 1 January 1998
    Publications and Reports
    International Evaluation Co-operation, Volume 8

    Present Status of Minor Actinide Data

    English WPEC NSC Nuclear science Nuclear data Nuclear science …
    Published date: 1 January 1999
    Publications and Reports
    International Evaluation Co-operation, Volume 9

    This report has been prepared by Subgroup 9 which was set up in 1998 with the aim of investigating discrepancies found between microscopic and macroscopic data for the uranium-235 fission neutron spe...

    English WPEC NSC Nuclear science Nuclear data Nuclear science …
    Published date: 15 July 2003
    Publications and Reports
    International Evaluation Co-operation, Volume 7

    Subgroup 7 of the NEA Working Party on International Nuclear Data Co-operation (WPEC) was established to re-evaluate the nuclear data standards cross-section. These cross-section data are the basis f...

    English WPEC NSC Nuclear science Nuclear data Nuclear science