• About us
  • Topics
  • News and resources
  • Learning and tools
×
Home
About us
  • About us
  • Topics
  • Topics
  • News and resources
  • News and resources
  • Learning and tools
  • Learning and tools
  • Copyright © 2020 OECD. All rights reserved.
    DATA BANK
    my nea
    1. Home
    2. Results page
    • Relevance
    • Date
    • Title
    Reset all
    Safety of components and structures
    Search
    80
    results
    Joint project
    Halden Human Technology Organisation (HTO) Project

    The Halden Reactor Project has been in operation since 1958 and is the oldest NEA joint project. It brings together an important international technical network in the area of nuclear safety ranging ...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 23 May 2023
    Joint project
    Component Operational Experience, Degradation and Ageing Programme (CODAP)

    Feeders on the Reactor Face in the Feeder Cabinet Photo: Canadian Nuclear Safety Commission (CNSC)

    The Component Operational Experience, Degradation and Ageing Programme (CODAP) combines the follow-u...

    Nuclear safety research LTO CSNI Safety of components and structures
    Published date: 21 October 2022
    Joint project
    Halden Reactor Project - Fuels and Material

    The Halden Reactor Project has been in operation at the Institute for Energy Technology (IFE) in Norway since 1958 and is the oldest NEA joint project. It brings together a large international techni...

    Nuclear fuel Nuclear safety research LTO CSNI Joint project Safety of components and structures …
    Published date: 17 October 2022
    Joint project
    Studsvik Material Integrity Life Extension (SMILE) Project

    Studsvik’s pool facility for storage and inspection of SMILE materials, left: 29 tonnes transportation flask, three pools each about 8 meters deep; and right: pool-in-pool for cutting and inspections...

    Long-term operation Nuclear safety research LTO Safety of components and structures
    Published date: 11 October 2022
    Activity
    Committee on the Safety of Nuclear Installations (CSNI)

    The Committee on the Safety of Nuclear Installations (CSNI) is responsible for NEA programmes and activities that support maintaining and advancing the scientific and technical knowledge base of the ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Safety of electrical systems External hazards and nuclear safety Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 5 October 2022
    Activity
    Working Group on Integrity and Ageing of Components and Structures (WGIAGE)

    The main mission of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) is to advance the current understanding of the relevant aspects related with ensuring the integrity...

    Structural materials WGIAGE Nuclear safety research Safety Safety of components and structures …
    Published date: 10 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
    CSNI Programme Review Group (CSNI PRG)

    The Programme Review Group is established to perform a programme quality review function within the Committee on the Safety of Nuclear Installations (CSNI) and to provide scientific assistance to the...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Safety of electrical systems External hazards and nuclear safety Nuclear safety research CSNI PRG CSNI Safety of components and structures …
    Published date: 7 July 2022
    News
    Long-term management and reliability of reactor core and containment cooling systems

    The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialist workshop entitled “Reactor core and containment cooling systems: Long-term management and reliability (RCC...

    News brief WGAMA Accident analysis and management Nuclear safety research Safety of components and structures Accident management …
    Published date: 29 October 2021
    Activity
    Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF)

    The Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF) was established at the June 2013 CSNI meeting to identify research activities to address safety research knowledge gaps...

    Fukushima Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 4 February 2021
    News
    New Joint Project: Studsvik Material Integrity Life Extension (SMILE)

    New Joint Project: Studsvik Material Integrity Life Extension (SMILE)

    News brief Nuclear safety research Safety of components and structures Safety research
    Published date: 26 January 2021
    Activity
    Task Group on Advanced Reactor Experimental Facilities (TAREF)

    A Task Group on Advanced Reactor Experimental Facilities (TAREF) had been set up to provide an overview of facilities suitable for carrying out safety research on gas-cooled and sodium fast reactors....

    Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 28 April 2020
    Activity
    Task Group on Sump Clogging

    The Task Group on Sump Clogging had been set up to update the State-of-the-art Report (SOAR) on Knowledge Base for Emergency Core Cooling System Recirculation Reliability issued in 1996, and with foc...

    Nuclear safety research CSNI Safety Safety of components and structures
    Published date: 28 April 2020
    Activity
    CSNI Action Plan in the Area of Safety Margins

    The CSNI Action Plan in the Area of Safety Margins was set up by the Committee on the Safety of Nuclear Installations (CSNI),

    Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Operating experience Nuclear safety regulation …
    Published date: 27 April 2020
    Activity
    Task Group on Safety Margin Applications and Assessment (SM2A)

    This task group was set up to carry out a pilot project using the methodology propsed in the final SMAP report published in 2007. In this pilot project, the SMAP methodology was applied to the Zion n...

    Accident analysis and management Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 27 April 2020
    Joint project
    Bubbler Condenser Project

    There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine. VVER-440/213 pressurised water reactors (PWRs) have a pressure...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures Accident management Pressurised water reactors Risk …
    Published date: 22 April 2020
    Joint project
    Loss-of-fluid Test (LOFT) Project

    The Loss-of-fluid Test (LOFT) Research Programme was originally set up by the US Nuclear Regulatory Commission. Part of the programme was later broadened into an international collaboration project u...

    Risk assessment Accident analysis and management Verification and validation Fuel cycle facility safety Validation Nuclear safety research Safety of components and structures Codes and programs Safety research …
    Published date: 22 April 2020
    Joint project
    Melt Coolability and Concrete Interaction (MCCI) Project

    In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...

    Risk assessment Light water reactors Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures Safety research …
    Published date: 22 April 2020
    Activity
    Senior Expert Group on Safety Research / Support Facilities for Existing and Advanced Reactors 2 (SESAR/SFEAR2)

    The Senior Expert Group on Safety Research / Support Facilities for Existing and Advanced Reactors 2 (SESAR/SFEAR2) is responsible for reviewing and updating the previous SESAR assessments of researc...

    Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Safety research …
    Published date: 22 April 2020
    Activity
    Task Group on Robustness of Electrical Systems of NPPs (ROBELSYS)

    A Task Group on the Robustness of Electrical Systems of NPPs in Light of the Fukushima Daiichi Accident (ROBELSYS) had been set up to improve the understanding of nuclear power plant electrical syste...

    Electrical systems Safety of electrical systems Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 22 April 2020
    Joint project
    PSB-VVER Project

    The PSB-VVER is a large-scale thermal-hydraulics testing facility operated by the Electrogorsk Research and Engineering Centre (EREC) in Russia. The PSB-VVER Project was intended to provide the exper...

    Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Joint project Safety of components and structures Codes and programs Pressurised water reactors Safety research …
    Published date: 22 April 2020
    Joint project
    Material Scaling (MASCA) Project

    The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident. Specifically, it addressed the influence of the chemical c...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Safety of components and structures …
    Published date: 22 April 2020
    Joint project
    RASPLAV Project

    The RASPLAV* Project was regarded as a successor to the Three Mile Island Vessel Investigation Project (TMI-VIP) completed in 1993. The TMI-VIP Project was set up to examine and assess the conditio...

    Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures …
    Published date: 22 April 2020
    Joint project
    Sandia Lower Head Failure Project

    During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subjected to significant thermal and pressure loads. The lower head has the potential to fail, releasing large amoun...

    Risk assessment Accident analysis and management Nuclear safety research Joint project Safety of components and structures …
    Published date: 21 April 2020
    Joint project
    Steam Explosion Resolution for Nuclear Applications (SERENA) Project

    The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Analysis and Management of Accidents (WGAMA) initiated a co-ordinated programme on Steam Explosion Resolution for Nuclear ...

    Risk assessment Accident analysis and management Information, data and knowledge management Nuclear safety research Ancillary data Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    Three Mile Island Reactor Pressure Vessel Investigation Project (TMI-VIP)

    On 28 March 1979, a partial meltdown of the Three Mile Island unit 2 (TMI-2) reactor occurred at the TMI nuclear power plant near Harrisburg, Pennsylvania, United States.

    A TMI accident evaluation pr...

    Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety of components and structures …
    Published date: 20 April 2020
    Joint project
    OECD-IAEA Paks Fuel Project

    During a fuel crud removal operation on the Paks-2 unit on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a special tank of the Paks Nuclear Power ...

    Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety of components and structures …
    Published date: 20 April 2020
    Other
    Improving regulatory practices through the OECD-NEA Stress Corrosion Cracking and Cable Ageing Project (SCAP)

    Paper about the Stress Corrosion Cracking and Cable Ageing Project (SCAP)

    English Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    Joint project
    Piping Failure Data Exchange (OPDE) Project

    The goals of the Piping Failure Data Exchange (OPDE) Project were to:

    • collect and analyse piping failure event data to promote a better understanding of underlying causes, impact on operations and s...
    Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    Joint project
    Cable Ageing Data and Knowledge (CADAK) Project

    In 2006, two subjects, stress corrosion cracking and the degradation of cable insulation were selected as the focus of the Stress Corrosion Cracking and Cable Ageing Project (SCAP). The project ran f...

    Nuclear safety research Joint project Safety of components and structures
    Published date: 17 April 2020
    Activity
    CSNI Task Group on Defence in Depth of Electrical Systems and Grid Interaction (DIDELSYS)

    The NEA Committee on the Safety of Nuclear Installations (CSNI) established a task group to examine Defence in Depth of Electrical Systems and Grid Interaction (DIDELSYS). The DIDELSYS Project, carri...

    Electrical systems Safety of electrical systems Nuclear safety research CSNI Safety Safety of components and structures …
    Published date: 17 April 2020
    Joint project
    Fire Incidents Records Exchange (FIRE) Project

    The main purpose of the project is to encourage multilateral co-operation in the collection and analysis of data relating to fire events. The objectives of the NEA Fire Project are to:

    • collect fire ...
    Accident analysis and management Fuel cycle facility safety External hazards and nuclear safety Nuclear safety research Databases CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 3 April 2020
    Joint project
    Behaviour of Iodine Project (BIP)

    The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment building following a severe accident. This...

    Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety Safety of components and structures Accident management Safety research …
    Published date: 2 April 2020
    Subtopic
    Safety of components and structures

    Reactor components and structures degrade by exposure to heat, environmental conditions and radiation. It is vital to understand ageing processes to ensure that safety criteria continue to be met.

    Nuclear safety research Safety Safety of components and structures Safety research
    Published date: 18 March 2020
    NEA Document
    ICDE Project Report: Summary Phase VII of the International Common-cause Exchange Project of Nuclear Power Plant Events
    NEA/CSNI/R(2019)3

    The ICDE project allows multiple countries to collaborate and exchange CCF data to enhance the quality of risk analyses, which include CCF modelling. Because CCF events are typically rare, most count...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 21 January 2019
    NEA Document
    Cable Ageing in Nuclear Power Plants: Report on the First and Second Terms (2012-2017) of the NEA Cable Ageing Data and Knowledge (CADAK) Project
    NEA/CSNI/R(2018)8

    The number of ageing nuclear power plants (NPPs) is increasing in NEA member countries. Accordingly, maintenance programmes, in-service inspection and testing of structures, systems and components im...

    English Nuclear safety research CSNI Safety of components and structures
    Published date: 6 December 2018
    NEA Document
    Lessons Learnt from Common-Cause Failure of Emergency Diesel Generators in Nuclear Power Plants: A Report from the International Common-Cause Failure Data Exchange (ICDE) Project
    NEA/CSNI/R(2018)5

    This report documents a study performed on a set of common-cause failure (CCF) events of Emergency Diesel Generators (EDG) at nuclear power plants. In May 2000, the ICDE Project published a report su...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Safety Safety of components and structures Safety research Risk assessment …
    Published date: 26 September 2018
    NEA Document
    Workshop on the Collection and Analysis of Emergency Diesel Generator Common-Cause Failures Impacting Entire Exposed Populations: International Common-Cause Failure Data Exchange (ICDE) Project Report
    NEA/CSNI/R(2017)8

    This report documents a study performed on a set of common-cause failure (CCF) events for diesel generators. The events were derived from the International CCF Data Exchange (ICDE) database and the s...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 24 August 2017
    Event
    Workshop on Developments in Fuel Cycle Facilities (FCFs) after the Fukushima Daiichi Nuclear Power Station (NPS) Accident
    15 - 18 November 2016
    Aomori City, Japan

    The Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Fuel Cycle Safety (WGFCS) held an international workshop on Developments in Fuel Cycle Facilit...

    Risk assessment Fukushima Accident analysis and management WGFCS Fuel cycle facility safety Nuclear safety research CSNI Safety Safety of components and structures Accident management …
    Published date: 4 May 2020
    NEA Document
    Workshop on Collection and Analysis of Common-Cause Failures due to External Factors: International Common-Cause Failure Data Exchange (ICDE) Project Report
    NEA/CSNI/R(2015)17

    In the light of the TEPCO Fukushima accident, this report documents a study performed on a set of common-cause failure (CCF) events due to external factors, meaning that not only storms and hurricane...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 20 October 2015
    NEA Document
    Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF Project): Phase I Summary Report
    NEA/CSNI/R(2015)18

    In 2012, following a proposal from Japan, the Committee on the Safety of Nuclear Installations (CSNI) decided to initiate a joint project to conduct a study of the accident progression for the Fukush...

    English Decommissioning Fukushima Accident analysis and management Decommissioning and legacy management Fuel cycle facility safety External hazards and nuclear safety Nuclear safety research CSNI Joint project Safety of components and structures Benchmark Accident management …
    Published date: 1 March 2015
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Centrifugal Pumps
    NEA/CSNI/R(2013)2

    The purpose of the International Common Cause Data Exchange (ICDE) Project is to allow multiple countries to collaborate and exchange Common Cause Failure (CCF) data to enhance the quality of risk an...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 4 July 2013
    NEA Document
    ICDE Project Report: Collection and Analysis of Common-cause Failures of Control Rod Drive Assemblies
    NEA/CSNI/R(2013)4

    The purpose of the ICDE Project is to allow multiple countries to collaborate and exchange common cause failure (CCF) data to enhance the quality of risk analyses that include CCF modelling. Because ...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 3 July 2013
    NEA Document
    Collection and Analysis of Common-cause Failures of Heat Exchangers: International Common-cause Failure Data Exchange (ICDE) Project Report
    NEA/CSNI/R(2015)11

    This report documents a study performed on a set of ICDE events related to heat exchangers. The events studied here had been collected in the ICDE database. Organisations from Canada, Germany, Japan,...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 1 April 2013
    NEA Document
    OECD-NEA Piping Failure Data Exchange Project (OECD-NEA OPDE) Final Report
    NEA/CSNI/R(2012)16

    Several OECD member countries agreed to establish the OECD/NEA Piping Failure Data Exchange Project (OECD/NEA OPDE) to encourage multilateral co-operation in the collection and analysis of data relat...

    English Nuclear safety research Databases CSNI Safety of components and structures …
    Published date: 26 November 2012
    NEA Document
    International Common Cause Failure Data Exchange (ICDE): General Coding Guidelines Updated Version
    NEA/CSNI/R(2011)12

    In this document, the general coding guidelines for the OECD NEA ICDE Project (International Common Cause Failure Data Exchange) are presented with explanations and appendices for each analysed compo...

    English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
    Published date: 21 February 2012
    Event
    International Workshop: Defence in Depth of Electrical Systems and Grid Interaction (DIDELSYS) Project
    10 - 11 May 2011
    OECD Conference Centre, Paris, France

    The July 2006 Forsmark-1 event identified a number of design deficiencies related to electrical power supply to systems and components important to safety in nuclear power plants. The CSNI establishe...

    Safety of electrical systems Nuclear safety research Safety of components and structures
    Published date: 4 May 2020
    NEA Document
    An Account of the OECD LOFT Project - May 1990
    NEA/CSNI(1990)181
    English Accident analysis and management Fuel cycle facility safety Nuclear safety research CSNI Safety of components and structures Codes and programs Risk Safety research Risk assessment Verification and validation Validation Accident management …
    Published date: 7 May 2010
    NEA Document
    Ageing Management of Thick-Walled Concrete Structures, Including ISI, Maintenance and Repair, Instrumentation Methods and Safety Assessment in View of LTO: Workshop Proceedings
    NEA/CSNI/R(2009)9

    The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) considered there was a need to review the state-of-the-art tech...

    English WGIAGE Nuclear safety research CSNI Safety of components and structures Proceedings …
    Published date: 14 December 2009
    NEA Document
    Ability of Current Advanced Codes to Predict Core Degradation, Melt Progression and Reflooding: Benchmark Exercise on an Alternative TMI-2 Accident Scenario
    NEA/CSNI/R(2009)3

    This Phase II exercise was the first benchmarking of severe accident codes promoted by NEA in almost 20 years. The objective of the exercise was to perform a code benchmark on a well-defined plant (s...

    English WGAMA Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety assessment CSNI Safety Safety of components and structures Risk assessment Benchmark Probabilistic risk assessment …
    Published date: 3 August 2009
    • <
    • 1
    • ...
    • >
    • 50 per page
      • 10 per page
      • 20 per page
      • 50 per page
      • All in one page
    Stay informed
    Receive monthly updates on NEA work, activities and newly released reports.
    SUBSCRIBE
    Follow us
    Follow the NEA on Twitter, LinkedIn, Facebook and YouTube.
    VACANCIES
    CONTACT AND PRACTICAL INFORMATION
    DATA BANK
    ACRONYMS
    ABOUT US
    History and statute
    Who we are
    What we do
    How we work
    Founding documents
    Privacy
    Terms
    TOPICS
    Nuclear safety research
    Nuclear safety regulation
    Human aspects of nuclear safety
    Radiological protection
    Radioactive waste management
    Decommissioning and legacy management
    Nuclear science
    Nuclear technology
    Nuclear economics
    Nuclear law
    NEWS AND RESOURCES
    News and events
    Publications and reports
    Projects
    Co-sponsored events
    LEARNING AND TOOLS
    Train with the NEA
    Databases, programs and tools
    Learn online
    NEA-SERVICED BODIES
    Generation IV International Forum (GIF)
    International Framework for Nuclear Energy Cooperation (IFNEC)
    Multinational Design Evaluation Programme (MDEP)
    Copyright © 2020 OECD. All rights reserved.
    Privacy
    Terms
    • en English
    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
    ub4sUuFXu77bvWAC