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    Activity
    Expert Group on Accident-tolerant Fuels for Light Water Reactors (EGATFL)

    The expert group primarily acted as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance.

    Fuel studies NSC Nuclear science Light water reactors EGATFL Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 18 October 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: 24 January 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: 17 January 2023
    Other
    Complementary material to “Role of Integral Experiment Covariance Data for Criticality Safety Validation: EG UACSA Benchmark Phase IV”
    English UACSA Criticality safety Criticality Benchmark …
    Published date: 17 January 2023
    Event
    20th Meeting of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)
    20 - 24 February 2023
    NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France)

    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 WPRS Multiphysics Radiation transport and shielding Thermal hydraulics and mechanics Reactor physics …
    Published date: 9 January 2023
    News
    NEA Data Bank trainings on SCALE and PHITS computer programs

    Courses were held in November 2022 in paris, France.

    News brief CPS Nuclear data Data Bank Training …
    Published date: 14 December 2022
    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) will be held in Sendai, Japan on 1-6 October 2023. Twenty years after the last conference in Japan, which was held in Tokai-mura...

    Criticality safety WPNCS Safety Co-sponsored event
    Published date: 13 December 2022
    News
    International Handbook of Evaluated Reactor Physics Benchmark Experiments

    The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.

    Physics News brief Experiments ICSBEP IRPhEP Reactor technology Reactor physics Reactor physics Benchmark …
    Published date: 13 December 2022
    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
    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
    Joint project
    Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)

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

    TCOFF Phases

    First Phase (2017-2020)

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

    Nuclear science Fission products Fukushima Thermodynamic data Nuclear safety research Safety research …
    Published date: 7 December 2022
    Activity
    Pressurised Water Reactor MOX/UO2 Core Transient Benchmark

    PWR MOX/UO2 Core Transient Benchmark

    Verification Benchmark Reactor physics
    Published date: 7 December 2022
    NEA Document
    Burnup Credit Criticality Benchmark Phase IIB: Burnup Calculations of Gadolinium-Bearing Fuel Rods in Boiling Water Reactor Assemblies for Storage and Transportation
    NEA/NSC/R(2022)3

    The NEA Expert Group on Used Nuclear Fuel criticality (EGUNF) organised a Phase IIB benchmark to re-examine code and nuclear data performance for BWR lattice calculations and focus on the depletion m...

    Criticality safety Nuclear science WPNCS Benchmark
    Published date: 30 November 2022
    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 fuel cycle EGFRW Fuel cycle physics and chemistry …
    Published date: 29 November 2022
    Activity
    MeshTal Viewer user manual

    MeshTal Viewer user manual

    Nuclear science
    Published date: 25 November 2022
    Activity
    JANIS

    JANIS (Java-based nuclear information software) is an application designed to facilitate the visualisation and manipulation of nuclear data. JANIS will be helpful to engineers and physicists who use ...

    Nuclear data Databases
    Published date: 24 November 2022
    News
    New edition: the International Handbook of Evaluated Criticality Safety Benchmark Experiments

    The 2021 edition can be downloaded online.

    Modelling and simulation Criticality safety Criticality Verification and validation Verification Validation ICSBEP Benchmark …
    Published date: 22 November 2022
    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: 21 November 2022
    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
    Activity
    International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook

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

    Modelling and simulation Criticality safety Verification and validation Verification Benchmark …
    Published date: 10 November 2022
    Activity
    International Criticality Safety Benchmark Evaluation Project (ICSBEP)

    The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allo...

    Criticality safety Nuclear science Criticality WPNCS ICSBEP …
    Published date: 10 November 2022
    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: 10 November 2022
    Activity
    International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE)

    The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at ...

    Modelling and simulation Reactor physics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 9 November 2022
    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 consists in a multi-staged code-to-code-to-data thermal hydraulics code validation...

    Thermal hydraulics Verification and validation Verification Validation Benchmark Reactor physics …
    Published date: 9 November 2022
    Subtopic
    Nuclear energy in the hydrogen economy

    As governments around the world are committing to reaching net zero emissions by 2050, many countries are looking at the role hydrogen can play in mitigating climate change. This page provides more i...

    Cogeneration Nuclear science Nuclear economics Hydrogen Nuclear technology Climate change Nuclear economics …
    Published date: 16 September 2022
    News
    Discussing radiation shielding, novel accelerator experiments and radiation physics simulations

    The event gathered 129 participants from 75 international institutions.

    Reactor physics News brief Nuclear science Radiation shielding EGPRS WPRS Radiation transport and shielding Reactor physics …
    Published date: 6 October 2022
    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 WPRS Reactor physics …
    Published date: 24 February 2021
    News
    Discussing scientific issues and uncertainty analysis of nuclear reactor systems

    WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.

    Nuclear fuel Reactor physics News brief Sodium-cooled reactor Light water reactors EGPRS WPRS Reactor physics Multiphysics …
    Published date: 9 June 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: 31 March 2020
    News
    First results from the QUENCH-ATF joint project

    The first QUENCH-ATF joint project test was successfully completed by the KIT team on 17 July 2022.

    News brief Nuclear science Joint project Accident Tolerant Fuels Accident tolerant fuels …
    Published date: 5 August 2022
    News
    Working Party on Nuclear Criticality Safety celebrates 25 years

    Over its 25 years of existence, the working party has contributed many topics and has led advances in criticality safety studies.

    News brief Criticality safety Nuclear science Criticality WPNCS …
    Published date: 28 July 2022
    News
    Resuming in-person training events with the FISPACT platform

    The NEA Data Bank's first in-person course since the pandemic started was on FISPACT, an enhanced multi-physics platform for neutron, proton, alpha, deuteron or gamma particle interactions.

    News brief Nuclear data
    Published date: 27 June 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 FIDES Experimental needs …
    Published date: 5 May 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
    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
    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 safety regulation Nuclear economics …
    Published date: 22 December 2016
    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
    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...

    EGPRS Radiation transport and shielding
    Published date: 19 October 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 EGPRS Pressurised heavy water reactors Reactor physics …
    Published date: 19 October 2022
    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 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 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 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 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 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 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 Proceedings
    Published date: 8 October 2013
    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 NSC Nuclear science Radiation shielding EGPRS Proceedings …
    Published date: 16 December 2021
    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
    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...

    Nuclear science Multiphysics Benchmark Multiphysics
    Published date: 11 October 2022
    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 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
    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
    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
    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
    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
    Published date: 8 August 2003
    Activity
    WPEC Expert Group on the High Priority Request List (EGHPRL) for Nuclear Data

    The expert group is responsible for managing the activities related to the High Priority Request List (HPRL) for nuclear data, in particular for guaranteeing that the entries are up-to-date and well-...

    WPEC Measurement NSC Nuclear science Nuclear data …
    Published date: 20 September 2022
    Activity
    WPEC Expert Group on the Recommended Definition of a General Nuclear Database Structure (EGGNDS)

    The expert group was established to develop a nuclear data structure definition that can meet the needs of a broad set of nuclear data users and providers.

    WPEC NSC Nuclear science Nuclear data
    Published date: 20 September 2022
    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
    Joint project
    Thermodynamics of Advanced Fuels - International Database (TAF-ID)

    On this page

    • Why is thermodynamic data for analyses involving nuclear fuel needed?
    • How is thermodynamic data calculated?
    • Available tools for thermodynamic calculations
    • Project organisation
    • TAF-ID i...
    Material science Structural materials Fuel studies Nuclear science Materials science Thermodynamic data TAF-ID …
    Published date: 31 March 2020
    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
    WPMM Expert Group on Validation and Benchmarks of Methods (EGVBM)

    The objectives of the expert group are to assess the accuracy and calculation time of the various first principle tools applied in the assessment of the properties of the nuclear materials; assess th...

    Material science WPMM NSC Nuclear science Materials science EGVBM …
    Published date: 5 March 2020
    Activity
    WPMM Expert Group on Primary Radiation Damage (EGPRD)

    The main objectives of this expert group are to assess the limitations of the NRT-dpa standard, in the light of both atomistic simulations and known experimental discrepancies; and to revisit the NRT...

    Material science WPMM NSC Nuclear science Materials science Radiation EGPRD …
    Published date: 5 March 2020
    Activity
    Pebble Bed Modular Reactor (PBMR) Coupled Neutronics/Thermal-hydraulics Transients Benchmark - PBMR-400 Core Design

    The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.

    SMR Gas-cooled reactors Thermal hydraulics Verification Multiphysics Benchmark Reactor physics Multiphysics …
    Published date: 26 July 2021
    Publications and Reports
    Physics of Plutonium Recycling - Volume II

    The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors. There are in addition incentives to better utilise fuel by increasing the b...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    Published date: 19 July 1995
    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 Validation Databases Benchmark Radiation transport and shielding Reactor physics …
    Published date: 4 August 2022
    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: 2 August 2022
    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: 2 August 2022
    Activity
    Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark

    Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark

    Verification and validation Verification Reactor physics
    Published date: 2 August 2022
    Activity
    OECD/NRC Benchmark based on NUPEC BWR Full-size Fine-mesh Bundle Tests (BFBT)

    NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark

    Thermal hydraulics Reactor physics
    Published date: 2 August 2022
    Activity
    Rostov-2 VVER-1000 Benchmark

    A number of tests with detail well documented neutronics and thermal-hydraulics measurements data have been performed at the Rostov Unit 2 (Rostov-2) nuclear power plant (NPP). The reactor type is a ...

    Reactor physics Nuclear science Multiphysics Multiphysics
    Published date: 2 August 2022
    Event
    WPRS Benchmarks Workshop 2023
    22 - 26 May 2023
    Bologna, Italy

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

    Nuclear science Reactor physics Reactor fuel performance
    Published date: 2 August 2022
    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: 2 August 2022
    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: 2 August 2022
    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: 2 August 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: 2 August 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: 2 August 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: 2 August 2022
    News
    Training event on Monte Carlo methods and radiation physics with the PENELOPE code

    The NEA Data Bank organised a PENELOPE training course at the University of Barcelona in Spain on 11-15 July 2022

    News brief Nuclear data Data Bank Training
    Published date: 1 August 2022
    Activity
    TVA Watts Bar Unit 1 Multi-Physics Benchmark

    TVA Watts Bar Unit 1 Multi-Physics Benchmark

    Nuclear science Benchmark
    Published date: 19 July 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: 19 July 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: 19 July 2022
    Activity
    McMaster Core Thermal-Hydraulics Benchmark

    Building on the 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 on U...

    Nuclear science Thermal hydraulics Verification and validation Validation Benchmark Reactor physics …
    Published date: 19 July 2022
    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: 19 July 2022
    Activity
    KALININ-3 Coolant Transient Benchmark

    This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-100...

    Verification and validation Verification Benchmark Reactor physics
    Published date: 19 July 2022
    Activity
    Boiling Water Reactor Turbine Trip (BWRTT) Benchmark

    The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...

    Thermal hydraulics Verification and validation Verification Uncertainty quantification Uncertainty analysis Reactor physics …
    Published date: 19 July 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 was hosted by CEA Cadarache in Aix-en-Provence. During the week of 30 May to 3 June...

    Thermal hydraulics and mechanics Reactor physics Reactor fuel performance
    Published date: 29 March 2022
    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: 5 July 2022
    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 safety regulation Nuclear economics …
    Published date: 10 September 2018
    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: 30 June 2022
    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: 26 May 2021
    Activity
    DATabase for IFpe (DATIF)

    DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NE...

    Nuclear fuel Physics Fuel studies NSC EGRFP Databases Ancillary data Reactor physics Integral experiments …
    Published date: 23 July 2020
    Activity
    High-Temperature Gas-Cooled Reactors

    High-temperature gas-cooled reactors (HTGRs), also known as very-high-temperature reactors (VHTR) are Generation IV reactors that can operate at very high temperatures and use a graphite-moderated ga...

    Cogeneration Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Reactor physics …
    Published date: 22 June 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: 2 June 2022
    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: 1 June 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
    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
    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
    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 EGAFCS Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 10 November 2016
    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
    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
    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
    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
    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
    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
    News
    Work on scientific issues around advanced nuclear fuel cycles

    Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) meeting, 8 June 2021.

    WPFC News brief Fuel studies Nuclear science Nuclear fuel cycle Partitioning and transmutation Fuel cycle physics and chemistry …
    Published date: 30 June 2021
    News
    Thermodynamic characterisation of severe accident analyses

    Preparatory meeting for Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)...

    News brief Nuclear science Fukushima Thermodynamic data TCOFF Nuclear safety research Joint project …
    Published date: 27 May 2021
    News
    NEA Thermodynamics of Advanced Fuels International Database updates

    NEA Thermodynamics of Advanced Fuels International Database updates

    News brief Nuclear science Thermodynamics Thermodynamic data TAF-ID …
    Published date: 25 January 2021
    News
    New NEA task force on partitioning and transmutation kicks off

    New NEA task force on partitioning and transmutation kicks off

    Nuclear science Advanced reactor systems Nuclear technology Actinides Radioactive waste management Fuel cycle technology Partitioning and transmutation Fuel cycle physics and chemistry Sustainable development and nuclear energy …
    Published date: 27 January 2021
    News
    Benchmarking, single and multi-physics modelling and simulation tools for nuclear reactor analysis

    NEA Working Party on Scientific Issues of Reactor Systems (WPRS) workshops, 7-15 December 2020.

    Reactor physics News brief Nuclear science Reactor physics
    Published date: 17 December 2020
    Subtopic
    Nuclear data

    Nuclear data refers to the probabilities, statistics and measurements of the physical interactions associated with atomic particles.

    Nuclear data
    Published date: 16 December 2019
    News
    New NEA reports on nuclear data evaluation

    New NEA reports on nuclear data evaluation

    News brief Nuclear energy data WPEC NSC Nuclear science Nuclear data …
    Published date: 5 August 2020
    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
    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 safety Benchmark Reactor physics …
    Published date: 1 June 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
    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
    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
    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
    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
    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
    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
    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
    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 Verification Reactor physics
    Published date: 4 June 2021
    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 safety regulation …
    Published date: 12 June 2020
    Activity
    Fluoride Salt-Cooled High-Temperature Reactor (FHR) Benchmark

    Fluoride salt-cooled high-temperature reactors (FHRs), cooled with liquid (molten) salt, fueled with TRISO-based fuel are a potential molten salt reactor (MSR) design.

    Nuclear science Molten salt reactors Verification Reactor physics
    Published date: 14 June 2021
    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 Benchmark Reactor physics Multiphysics …
    Published date: 7 July 2006
    Publications and Reports
    NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark - Volume II

    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 Modelling and simulation Reactor physics Light water reactors Verification and validation Validation Uncertainty analysis Benchmark Reactor physics …
    Published date: 1 January 2010
    Activity
    Technical Review Group for the International Assay Data of Spent Nuclear Fuel Database (TRG SFCOMPO)

    The Technical Review Group (TRG) for the International Assay Data of Spent Nuclear Fuel Database (SFCOMPO) lies under the direction of the Working Party on Nuclear Criticality Safety (WPNCS).

    Criticality safety
    Published date: 13 April 2021
    Activity
    MeshTal Viewer

    MeshTal Viewer is a Java based software which can read mesh tallies output formats of several neutron transport codes and display them graphically.

    Nuclear science Verification
    Published date: 2 October 2020
    Other
    Nuclear Education, Skills & Technology (NEST) Framework
    Nuclear science Nuclear Education, Skills and Technology (NEST) Framework
    Published date: 21 June 2016
    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
    Activity
    Expert Group on Integral Experiments for Minor Actinide Management (EGIEMAM)

    The expert group critically reviewed integral experiments for validating minor actinide (MA) nuclear data, recommended additional integral experiments needed for validating MA nuclear data and invest...

    WPFC WPEC Nuclear science Experiments Actinides WPRS Reactor physics Integral experiments Minor actinides NSC Nuclear fuel cycle Fuel cycle physics and chemistry …
    Published date: 5 March 2021
    Activity
    Sodium-cooled Fast Reactor (SFR) Benchmark Task Force

    A sodium-cooled fast reactor (SFR) is a fast neutron reactor that uses molten sodium metal as a coolant. Sodium-cooled Fast Reactors (SFRs) are the most promising type of reactors to achieve Generati...

    Reactor physics EGRPANS Fast reactor WPRS Reactor physics …
    Published date: 4 February 2021
    Other
    ICNC2019Workshop
    Nuclear science
    Published date: 1 February 2021
    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: 30 January 2021
    Activity
    IRPhE Handbook 2019 Edition - Contents

    IRPhE Handbook 2019 Edition - Contents

    Verification and validation Verification Uncertainty quantification Uncertainty analysis Reactor physics …
    Published date: 30 September 2020
    Activity
    Expert Group on Improvement of Integral Experiments Data for Minor Actinide Management (EGIEMAM-II)

    The expert group works in co-ordination with Working Party on Scientific Issues of Reactor Systems (WPRS) [including the IRPhE Project], Working Party on Scientific Issues of the Fuel Cycle (WPFC) an...

    WPEC NSC Nuclear science Experiments Actinides WPRS Nuclear fuel cycle Reactor physics Fuel cycle physics and chemistry Integral experiments Minor actinides …
    Published date: 9 March 2020
    Activity
    3-D Radiation Transport benchmarks

    3-D Radiation Transport benchmarks dealt with scientific issues in the field of deterministic and stochastic methods and computer codes relative to three dimensional (3-D) radiation transport. 

    Reactor physics Monte Carlo method Transport Verification and validation Radiation shielding Radiation Validation Benchmark Reactor physics …
    Published date: 30 September 2020
    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 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 Benchmark Multiphysics …
    Published date: 23 February 2007
    Subtopic
    Multiphysics

    Multiphysics are simulations using computer applications or software to couple multiple physical events in order to predict or validate the physical real-world outcome.

    Multi-physics simulations Nuclear science Benchmark Reactor physics Multiphysics …
    Published date: 16 October 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 8 (LWR-UAM-8)
    14 - 16 May 2014
    Garching, Germany
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 21 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 1 (LWR-UAM-1)
    10 - 11 May 2007
    Paris, France
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 2 (LWR-UAM-2)
    2 - 4 April 2008
    Garching, Germany
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 4 (LWR-UAM-4)
    13 - 15 April 2010
    Pisa, Italy
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 5 (LWR-UAM-5)
    13 - 15 April 2011
    Stockholm, Sweden
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 6 (LWR-UAM-6)
    9 - 11 May 2012
    Karlsruhe, Germany
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 9 (LWR-UAM-9)
    20 - 22 May 2015
    Madrid, Spain
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 11 (LWR-UAM-11)
    10 - 12 May 2017
    Erlangen, Germany
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 12 (LWR-UAM-12)
    16 - 17 May 2018
    Lucca, Italy
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 13 (LWR-UAM-13)
    13 - 17 May 2019
    Oak Ridge, United States
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 3 (LWR-UAM-3)
    29 April 2009 - 1 May 2009
    University Park/State College, Pennsylvania, United States
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs - Workshop 10 (LWR-UAM-10)
    1 - 3 June 2016
    Villigen, Switzerland
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Event
    Uncertainty Analysis in Modelling Workshop (UAM-2006)
    28 - 29 April 2006
    Pisa, Italy
    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 18 December 2020
    Other
    Kalinin-3 Coolant Transient Benchmark - Conditions for release 2020

    Conditions for release, rules and restrictions applying to the Kalinin Unit 3 (Kalinin-3) Transient Benchmark caused by the switching-off of one of the four operating main circulation pumps (MCPs) at...

    Benchmark Reactor physics
    Published date: 30 September 2020
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume III

    This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 22 November 2002
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume II

    The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 22 December 2000
    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 Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 1 January 1999
    Publications and Reports
    Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume IV

    This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

    English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
    Published date: 19 November 2003
    Activity
    Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors (LWRs) workshops

    The Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors (LWRs) is an international high-visibility benchmark for unce...

    Boiling water reactors Light water reactors Reactor physics Modelling and simulation Reactor physics Verification and validation Verification Validation Uncertainty analysis Benchmark Pressurised water reactors …
    Published date: 30 September 2020
    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 Modelling and simulation NSC Thermal hydraulics Benchmark Thermal hydraulics and mechanics …
    Published date: 19 June 2013
    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 Benchmark Pressurised water reactors …
    Published date: 20 January 2006
    Activity
    International Fuel Performance Experiments (IFPE) database

    International Fuel Performance Experiments (IFPE) is the public domain database on 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 August 2020
    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
    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: 6 November 2020
    Activity
    WPMM Expert Group on Multi-scale Modelling of Fuels (EGM2F)

    Under the guidance of the Nuclear Science Committee (NSC) and under the mandate of the Working Party on Multi-scale Modelling of Fuels and Structural Materials for Nuclear Systems (WPMM), the objecti...

    WPMM NSC Nuclear science Materials science EGM2F …
    Published date: 5 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
    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 Benchmark Radiation transport and shielding …
    Published date: 17 March 2000
    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 Reactor physics
    Published date: 4 March 2020
    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
    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 Reactor physics …
    Published date: 22 August 2006
    Publications and Reports
    Minor Actinide Burning in Thermal Reactors

    This publication provides an introduction to minor actinide nuclear properties and discusses some of the arguments in favour of minor actinide recycling, as well as the potential role of thermal reac...

    English Fuel studies Nuclear science Reactor physics Fuel cycle physics and chemistry Minor actinides …
    Published date: 18 November 2013
    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 Reactor physics Fuel studies Sodium-cooled reactor NSC Generation IV reactors Benchmark Reactor physics …
    Published date: 5 November 2015
    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 Reactor physics Multiphysics Reactor physics Cogeneration NSC Gas-cooled reactors Benchmark …
    Published date: 18 January 2019
    Activity
    Expert Group on Reactor-based Plutonium Disposition (TFRPD)

    The Expert Group on Reactor-based Plutonium Disposition (TFRPD) dealt with the status and trends of reactor physics, fuel performance and fuel cycle issues related to the disposition of weapons-grade...

    Reactor physics Fuel studies Nuclear science Plutonium Reactor physics …
    Published date: 16 December 2020
    Subtopic
    Radiation transport and shielding

    Radiation shielding is a protective shield that is inserted betweeen a source of ionising radiation and the object to protect to reduce the amount of damage that can happen to delicate or biological ...

    Nuclear science Radiation shielding
    Published date: 16 October 2020
    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 Reactor physics …
    Published date: 10 December 2020
    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
    Published date: 1 January 1991
    Publications and Reports
    Reactor Noise - SMORN II
    English Reactor physics Nuclear science Proceedings
    Published date: 1 January 1977
    Publications and Reports
    Reactor Noise - SMORN I
    English Reactor physics Nuclear science Proceedings
    Published date: 1 January 1974
    Activity
    Expert Group on Needs of Research and Test Facilities in Nuclear Science

    The Nuclear Science Committee (NSC), through its expert group, conducted a study on research and development (R&D) needs in nuclear science, held a workshop on R&D needs for current and future nuclea...

    R&D Nuclear science Reactor technology Safety research
    Published date: 30 September 2020
    Activity
    High Burn-up Fuel in Light Water Reactors (LWRs)

    Historically, average discharge burn-ups in light water reactors (LWRs) have steadily increased with time as experience has accumulated and technological developments have progressed. The main benefi...

    Fuel studies Nuclear science Light water reactors
    Published date: 30 September 2020
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 1 (Vol. 1)

    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 Multiphysics Benchmark Reactor physics Pressurised water reactors …
    Published date: 31 December 2003
    Subtopic
    Fuel cycle physics and chemistry

    The nuclear fuel cycle is the chain of processes whereby nuclear fuel is prepared and managed before and after its use in a reactor.

    Nuclear fuel Fuel studies Accident tolerant fuels Fuel cycle physics and chemistry
    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
    Published date: 10 March 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
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 1 (Vol. 2)

    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 Multiphysics Benchmark Reactor physics Pressurised water reactors Multiphysics …
    Published date: 30 June 2006
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 1 (Vol. 3)

    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
    Published date: 16 November 2007
    Publications and Reports
    VVER-1000 Coolant Transient Benchmark - Phase 2 (Ex. 1)

    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 Nuclear science
    Published date: 5 October 2010
    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 Reactor physics NSC Multiphysics Benchmark Reactor physics Pressurised water reactors …
    Published date: 4 January 2012
    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 NSC Nuclear science Multiphysics Benchmark Reactor physics Pressurised water reactors …
    Published date: 2 October 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 NSC Nuclear science Multiphysics Benchmark Reactor physics …
    Published date: 24 June 2015
    Publications and Reports
    Basic Studies in the Field of High-temperature Engineering

    In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) and the need for improved knowledge of materials for nuclear applications that resist high temperatures, the NEA or...

    English Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Proceedings Reactor physics …
    Published date: 1 January 2000
    Publications and Reports
    Basic Studies in the Field of High-temperature Engineering

    In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, th...

    English Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Proceedings Reactor physics …
    Published date: 29 May 2002
    Publications and Reports
    Basic Studies in the Field of High-temperature Engineering

    In response to growing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the N...

    English Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Proceedings Reactor physics …
    Published date: 1 June 2004
    Activity
    Expert Group on Radiation Transport and Shielding (EGRTS)

    Under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS), the expert group performed specific tasks associated with radiation transport and shielding aspects of current ...

    EGRTS State-of-the-art report Benchmark Reactor physics
    Published date: 3 March 2020
    Activity
    Dosimetry benchmarks and radiation damage of materials under irradiation

    The page describes the NEA's work on computing radiation dose and modelling of radiation-induced degradation of reactor components.

    Benchmark Reactor physics
    Published date: 30 September 2020
    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 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 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
    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 Benchmark Reactor physics …
    Published date: 1 January 2000
    Event
    Second Information Exchange Meeting on the Nuclear Production of Hydrogen
    2 - 3 October 2003
    Argonne National Laboratory, Illinois, USA

    As growing demand for energy has prompted ever-increasing use of fossil fuels, the resulting issues of energy security and climate change have in turn led to renewed interest in the use of hydrogen a...

    Nuclear science Multiphysics Reactor physics
    Published date: 2 October 2003
    Event
    Third Information Exchange Meeting on the Nuclear Production of Hydrogen
    5 - 7 October 2005
    Japan Atomic Energy Agency, Oarai, Japan

    The NEA Nuclear Science Committee (NSC) had organised two previous information exchange meetings on the nuclear production of hydrogen. The last of these meetings was held in October 2003, where deve...

    Nuclear science Multiphysics Reactor physics
    Published date: 5 October 2005
    Event
    Fourth information Exchange Meeting on the Nuclear Production of Hydrogen
    14 - 16 April 2009
    Chicago, Illinois, United States

    The NEA Nuclear Science Committee (NSC) had previously organised three information exchange meetings to discuss scientific and strategic matters pertaining to the nuclear production of hydrogen. Earl...

    Nuclear science Multiphysics Reactor physics
    Published date: 14 April 2009
    Other
    Fourth Information Exchange Meeting on thr Nuclear Production of Hydrogen - Programme

    Fourth Information Exchange Meeting on thr Nuclear Production of Hydrogen, 13-16 April 2009, Oakbrook, IL, USA - Programme

    Nuclear science Multiphysics Reactor physics
    Published date: 24 November 2020
    Other
    First Information Exchange Meeting on the Nuclear Production of Hydrogen - Programme and abstracts

    First Information Exchange Meeting on the Nuclear Production of Hydrogen, Paris, France, 2-3 October, 2000 - Programme and abstracts

    Nuclear science Multiphysics Reactor physics
    Published date: 24 November 2020
    Other
    Third Information Exchange Meeting on the Nuclear Production of Hydrogen - Programme

    Third Information Exchange Meeting on the Nuclear Production of Hydrogen including Second HTTR Workshop, Japan Atomic Energy Agency (JAEA), Oarai, Japan, 5 - 7 October 2005 - Programme

    Nuclear science Multiphysics Reactor physics
    Published date: 24 November 2020
    Publications and Reports
    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...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    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 Benchmark Reactor physics Multiphysics …
    Published date: 7 July 2005
    Publications and Reports
    Boiling Water Reactor Turbine Trip (TT) Benchmark - Volume III

    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 Benchmark Reactor physics Multiphysics …
    Published date: 21 December 2006
    Publications and Reports
    Physics of Plutonium Recycling - Volume V

    Studies on fast reactors have historically concentrated on their capability to use plutonium produced in thermal reactors as initial fuel, and subsequently their capacity to produce electricity while...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    Published date: 1 November 1996
    Publications and Reports
    Physics of Plutonium Recycling - Volume IV

    Studies on fast reactors have historically concentrated on their capability of using plutonium produced in thermal reactors as initial fuel, and subsequently their capacity to produce electricity whi...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    Published date: 1 November 1995
    Publications and Reports
    Physics of Plutonium Recycling - Volume III

    The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors, requiring an increase in the total loading necessary in mixed plutonium-ura...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    Published date: 17 November 2020
    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 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 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 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 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 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 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
    Published date: 8 October 2010
    Publications and Reports
    Physics of Plutonium Recycling - Volume IX

    The NEA has studied multiple recycling issues associated with various reactor systems fuelled with mixed-oxide (MOX) and published a series of computational physics benchmarks. This has led to improv...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    Published date: 21 June 2007
    Publications and Reports
    Physics of Plutonium Recycling - Volume VIII

    The NEA has studied multiple recycling issues associated with various reactor systems fuelled with mixed-oxide (MOX) and published a series of computational physics benchmarks. This has led to improv...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    Published date: 21 June 2007
    Publications and Reports
    Physics of Plutonium Recycling - Volume VII

    The commercial recycling of plutonium as PUO2/UO2 mixed-oxide (MOX) fuel is an established practice in pressurised water reactors (PWRs) in several countries, the main motivation being the consumptio...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    Published date: 10 March 2003
    Publications and Reports
    Physics of Plutonium Recycling - Volume VI

    Although the recycling of plutonium as thermal mixed-oxide (MOX) fuel in pressurised water reactors (PWRs) is now well-established on a commercial scale, many physics questions remain. The main quest...

    English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
    Published date: 23 October 2002
    Publications and Reports
    Plutonium Management in the Medium Term

    The decision to re-use plutonium generated in thermal reactors is a strategic one for a utility, and is closely tied to the spent fuel management strategy. One option is to reprocess the spent fuel i...

    English Nuclear science
    Published date: 3 November 2003
    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
    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
    Published date: 9 February 2004
    News
    Experimental criticality safety benchmarks

    The ICSBEP Technical Review Group of over 65 international technical experts met remotely for the first time on 19-23 October 2020.

    News brief Criticality safety Nuclear science Criticality ICSBEP …
    Published date: 4 November 2020
    Publications and Reports
    International Evaluation Co-operation, Volume 31

    Meeting Nuclear Data Needs for Advanced Reactor Systems

    English WPEC NSC Nuclear science