• 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 © 2023 OECD. All rights reserved.
    DATA BANK
    my nea
    1. Home
    2. Results page
    • Relevance
    • Date
    • Title
    Reset all
    CSNI
    Search
    9368
    results
    NEA Document
    Comparison of Methodologies for the Simulation of Electrical Systems in Nuclear Power Plants: Working Group on Electrical Power Systems Activity 3 Report
    NEA/CSNI/R(2018)10

    One of the major conclusions of this workshop was that simulation of electrical systems has not been adequately discussed at the international level despite the fact that it is used more and more fre...

    English WGELEC Nuclear safety research CSNI
    Published date: 19 February 2019
    NEA Document
    NEA Benchmark Exercise: Computational Fluid Dynamic Prediction and Uncertainty Quantification of a GEMIX Mixing Layer Test
    NEA/CSNI/R(2017)19
    The main objectives of the current activity are the promotion, test and evaluation of various methodologies for uncertainty quantification in computational fluid dynamics (UQCFD) for nuclear reactor...
    English Uncertainty quantification Nuclear safety research CSNI
    Published date: 6 February 2019
    NEA Document
    Phase II of the Assessment of Structures Subjected to Concrete Pathologies (ASCET): Final Report
    NEA/CSNI/R(2018)4

    The objective of the CSNI ASCET activity is to make general recommendations for ageing management of concrete nuclear facilities taking into account the effect of concrete pathologies on structural d...

    English WGIAGE Nuclear safety research CSNI
    Published date: 21 January 2019
    NEA Document
    NEA Component Operational Experience, Degradation & Ageing Programme (CODAP): Second Term (2015-2017) Status Report
    NEA/CSNI/R(2019)7
    Several Nuclear Energy Agency (NEA) member countries have agreed to establish the Component Operational Experience, Degradation and Ageing Programme (CODAP) to encourage multilateral co-operation in...
    English Nuclear safety research CSNI
    Published date: 21 January 2019
    NEA Document
    Phase II of the Assessment of Structures Subjected to Concrete Pathologies (ASCET): Final Report (Appendix)
    NEA/CSNI/R(2018)4/ADD1

    Increasingly engineers are confronted with the need to perform predictive structural assessment based on limited or incomplete data set. This may include damage up to failure assessment (in the conte...

    English WGIAGE Nuclear safety research CSNI
    Published date: 1 January 2019
    NEA Document
    Status of Practice for Level 3 Probabilistic Safety Assessments
    NEA/CSNI/R(2018)1

    The mission of the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) is to advance understanding of probabilistic safety as...

    English WGRISK Nuclear safety research CSNI
    Published date: 19 December 2018
    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
    Resolving Complex Safety Relevant Issues Related to Hydrogen Release in Nuclear Power Plant Containments During a Postulated Severe Accident
    NEA/CSNI/R(2018)11

    This is a summary report by the Hydrogen Mitigation Experiments for Reactor Safety (HYMERES) project on the PANDA and MISTRA experiments.

    Phase 1 of the Project, between 2013 and 2016, focused on imp...

    English Nuclear safety research CSNI Joint project
    Published date: 23 November 2018
    NEA Document
    Integrity of Structures, Systems and Components Under Design and Beyond Design Loads in Nuclear Power Plants: Final Report of the Project on Metallic Component Margins Under High Seismic Loads (MECOS)
    NEA/CSNI/R(2018)3

    The Metallic Component Margins under High Seismic Loads (MECOS) Project is an international programme organised under an initiative of the NEA. The main objective of the MECOS Project is to quantify ...

    English WGIAGE Nuclear safety research CSNI
    Published date: 12 November 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
    Informing Severe Accident Management Guidance and Actions for Nuclear Power Plants through Analytical Simulation
    NEA/CSNI/R(2017)16

    This report by the Working Group on Analysis and Management of Accidents (WGAMA) summarises the first Nuclear Energy Agency (NEA) project to address the topic of severe accident management guidance (...

    English WGAMA Accident analysis and management Nuclear safety research CSNI …
    Published date: 2 July 2018
    NEA Document
    Phenomena Identification and Ranking Table: R&D Priorities for Loss-of-Cooling and Loss-of-Coolant Accidents in Spent Nuclear Fuel Pools
    NEA/CSNI/R(2017)18
    The main objective of the report is to identify research and development priorities related to loss-of-cooling and loss-of-coolant accidents in spent fuel pools. This is done by applying a PIRT proc...
    English Spent fuel Nuclear safety research CSNI WGFS …
    Published date: 11 June 2018
    NEA Document
    Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors: Proceedings of a WGFS Workshop
    NEA/CSNI/R(2018)9

    This report documents the proceedings of the Workshop on Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors held in Lucca, Italy on 22-24 June 2016. The workshop was organised jointly by the ...

    English Nuclear safety research CSNI Proceedings WGFS …
    Published date: 11 June 2018
    NEA Document
    Operating Experience Insights into Below Ground Piping at Nuclear Power Plants: A Topical Report by the NEA Component Operational Experience, Degradation and Ageing Programme
    NEA/CSNI/R(2018)2

    Structural integrity of piping systems is important for safety and operability of nuclear plants. In recognition of this, information on degradation and failure of piping components and systems is co...

    English Nuclear safety research CSNI PRG CSNI
    Published date: 24 May 2018
    Event
    International Workshop on Chemical Hazards in Fuel Cycle Facilities Nuclear Processing
    17 - 19 April 2018
    Boulogne-Billancourt, France

    Hosted by the French Institute for Radiological Protection and Nuclear Safety (IRSN) and the Nuclear Energy Agency (NEA)

    Objectives

    Working under the mandate of the CSNI, the objective of the WGFCS i...

    Risk assessment Accident analysis and management WGFCS Fuel cycle facility safety Nuclear safety research CSNI Safety …
    Published date: 30 April 2020
    NEA Document
    Understanding the Impact of External Hazards on Nuclear Facilities: Severe Weather and Storm Surge
    NEA/CSNI/R(2017)13
    The March 2011 accident at Fukushima Daiichi nuclear power plant triggered discussions about the natural external events that are low-frequency but high-consequence. In order to address these issues...
    English WGEV Nuclear safety research CSNI Proceedings …
    Published date: 16 April 2018
    NEA Document
    Summary Report of the NEA Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS) Joint Project
    NEA/CSNI/R(2017)9

    The NEA Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS) Project is one of the NEA supported joint projects under the auspices and with the support of the NEA. It started from Apr...

    English Nuclear safety research CSNI Joint project
    Published date: 11 April 2018
    NEA Document
    Status Report on Ex-Vessel Steam Explosion
    NEA/CSNI/R(2017)15
    The Status Report on Ex-Vessel Steam Explosion (EVSE) summarises the significant progress made in the field of Fuel Coolant Interaction/Steam Explosion (FCI/SE) knowledge during these last ten years...
    English Nuclear safety research CSNI
    Published date: 1 March 2018
    NEA Document
    Summary and Conclusions of the Joint PKL3-ATLAS Workshop on Analytical Activities
    NEA/CSNI/R(2017)10

    The workshop was held in Lucca, Italy on 13-15 April 2016.

    The PKL3 Project tests consisted of a programme of experiments intended to, inter alia, understand complex heat transfer mechanisms in the s...

    English Nuclear safety research CSNI Joint project
    Published date: 31 January 2018
    NEA Document
    Solving Thermal Hydraulic Safety Issues for Current and New Pressurised Water Reactor Design Concepts: Primary Coolant Loop Test Facility (PKL2) Project – Final Report
    NEA/CSNI/R(2017)6

    For many years, extensive experimental investigations into the system response of pressurised water reactors (PWRs) under accident conditions have been being conducted at the large-scale Primärkreisl...

    English Nuclear safety research CSNI Pressurised water reactors
    Published date: 17 January 2018
    NEA Document
    Investigating Heat and Smoke Propagation Mechanisms in Multi-Compartment Fire Scenarios: Final Report of the PRISME Project
    NEA/CSNI/R(2017)14
    Fire hazards analyses (FHA) and probabilistic fire safety analyses (Fire PSA) have demonstrated that fire may be an important contributor to core damage frequency and other major plant damage states...
    English Nuclear safety research CSNI
    Published date: 11 January 2018
    NEA Document
    Developments in Fuel Cycle Facilities after the Fukushima Daiichi Nuclear Power Station Accident: Workshop Proceedings
    NEA/CSNI/R(2017)12
    The main objective of the workshop, held in Aomori City, Japan on 15-17 November 2016, was to review and discuss national activities, plans and regulatory approaches by member countries in light of ...
    English Fuel cycle facility safety Nuclear safety research CSNI Proceedings …
    Published date: 8 January 2018
    NEA Document
    Developments in Fuel Cycle Facilities after the Fukushima Daiichi Nuclear Power Station Accident: Workshop Proceedings (Appendix 3)
    NEA/CSNI/R(2017)12/ADD1

    The workshop was held in Aomori City, Japan on 15-17 November 2016.

    On 11 March 2011, the Tohoku-Taiheiyou-Oki earthquake occurred near the east coast of Honshu, Japan. This magnitude 9.0 earthquake ...

    English Fuel cycle facility safety Nuclear safety research CSNI Proceedings …
    Published date: 1 January 2018
    NEA Document
    Benchmark Results on the Analytical Evaluation of the Fracture Mechanic Parameters K and J
    NEA/CSNI/R(2017)11

    For most nuclear design and in-service inspection codes, fracture mechanics is used to evaluate the integrity of cracked components. The major parameters used in this kind of analysis are K and J whi...

    English WGIAGE Nuclear safety research CSNI
    Published date: 1 November 2017
    NEA Document
    Probabilistic Safety Assessment Insights Relating to the Loss of Electrical Sources
    NEA/CSNI/R(2017)5

    The main objective of the Working Group on Risk Assessment (WGRISK) is to advance Probabilistic Safety Assessment (PSA) understanding and to enhance its use for improving the safety of nuclear instal...

    English WGRISK Nuclear safety research CSNI
    Published date: 1 September 2017
    NEA Document
    Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark: Final Report
    NEA/CSNI/R(2016)18

    PREMIUM is the follow-up of a series of projects promoted by NEA/CSNI and focused on the issue of best estimate plus uncertainty (BEPU) analysis of thermo-hydraulic accident scenarios in nuclear plan...

    English WGAMA Nuclear safety research CSNI Benchmark …
    Published date: 24 August 2017
    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
    NEA Document
    Fatigue of Nuclear Reactor Components: Proceedings of the 4th International Conference (Appendix 4)
    NEA/CSNI/R(2017)2/ADD1

    International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain.

    In this work, a complete algorithm for monitoring fatigue was developed for nuclear...

    English WGIAGE Nuclear safety research CSNI Proceedings …
    Published date: 17 July 2017
    NEA Document
    Fatigue of Nuclear Reactor Components: Proceedings of the 4th International Conference
    NEA/CSNI/R(2017)2

    This is a summary report from the International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain. Over 90 specialists from 21 countries attended th...

    English WGIAGE Nuclear safety research CSNI Proceedings …
    Published date: 17 July 2017
    NEA Document
    Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET)
    NEA/CSNI/R(2016)13

    Taking into account life extension, concrete degradation becomes one of the main issues for long-term operation (LTO). Concrete pathologies/degradation mechanisms – alkali-aggregate reaction (AAR), d...

    English WGIAGE Nuclear safety research CSNI
    Published date: 4 July 2017
    NEA Document
    Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET): Appendices 3 and 4
    NEA/CSNI/R(2016)13/ADD1

    Taking into account life extension of nuclear power plants (NPPs) there is a need to investigate degradation mechanisms of existing structures defining their aging management program. The Alkali Aggr...

    English WGIAGE Nuclear safety research CSNI
    Published date: 1 July 2017
    NEA Document
    Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications: Proceedings of the Expert Workshop
    NEA/CSNI/R(2016)17

    The theme of this workshop, held in Charlotte, United States on 19-21 February 2015, was “Establishing Reasonable Confidence in the Human Factors Validation of Main Control Room Systems of Nuclear Po...

    English Human aspects of nuclear safety WGHOF Nuclear safety research CSNI Human and organisational factors Proceedings …
    Published date: 2 June 2017
    NEA Document
    Final Integration Report of the Rig-of-Safety Assessment (ROSA-2) Project (2009-2012)
    NEA/CSNI/R(2016)10
    The use of computer codes is required in safety evaluation of light water reactors (LWRs) in order to simulate plant behaviour during design basis event (DBE) and beyond-DBE (BDBE). This involves co...
    English Nuclear safety research CSNI
    Published date: 1 June 2017
    NEA Document
    Report on the Testing Phase (2014-2016) of the High Energy Arcing Fault Events (HEAF) Project: Experimental Results from the International Energy Arcing Fault Research Programme
    NEA/CSNI/R(2017)7
    This report documents an experimental programme designed to investigate the High Energy Arcing Fault (HEAF) phenomena. The most recent international nuclear power plant (NPP) operating experience wi...
    English Nuclear safety research CSNI Joint project
    Published date: 23 May 2017
    NEA Document
    Reactivity-initiated Accident Fuel-rod-code Benchmark Phase II: Uncertainty and Sensitivity Analyses
    NEA/CSNI/R(2017)1
    English CSNI
    Published date: 22 May 2017
    NEA Document
    Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications: Proceedings of the Expert Workshop (Appendix C)
    NEA/CSNI/R(2016)17/ADD2

    Thisi document contains Appendix C of the Proceedings of the Expert Workshop on Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications held in Charlotte, United States...

    English WGHOF Nuclear safety research CSNI Proceedings …
    Published date: 1 March 2017
    NEA Document
    Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications: Proceedings of the Expert Workshop (Appendix B)
    NEA/CSNI/R(2016)17/ADD1

    This document is Appendix B of the Proceedings of the Expert Workshop on Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications, held in Charlotte, United States on 19...

    English WGHOF Nuclear safety research CSNI Proceedings …
    Published date: 1 March 2017
    NEA Document
    A State-of-the-Art Report on Scaling in System Thermal-hydraulics Applications to Nuclear Reactor Safety and Design
    NEA/CSNI/R(2016)14

    The present document deals with scaling in nuclear-system thermal hydraulics (SYS TH), including the connection with nuclear-reactor safety technology (NST). Scaling has constituted “an issue” since ...

    English WGAMA Nuclear safety research CSNI
    Published date: 1 March 2017
    NEA Document
    Safety Research Opportunities Post-Fukushima: Initial Report of the Senior Expert Group
    NEA/CSNI/R(2016)19

    One of the imperatives following the accident at the Fukushima Daiichi nuclear power station is for the nuclear science and industry communities to ensure that knowledge gaps in nuclear safety are id...

    English Fukushima Nuclear safety research CSNI
    Published date: 1 February 2017
    NEA Document
    Aerosol and Iodine Issues, and Hydrogen Mitigation under Accidental Conditions in Water-cooled Reactors: Thermal-hydraulics, Hydrogen, Aerosols and Iodine (THAI-2) Project – Final Report
    NEA/CSNI/R(2016)8

    The overall objective of the THAI-2 project is to address open questions concerning the behaviour of hydrogen, iodine and aerosols in the containment of water-cooled reactors during design-basis or s...

    English Nuclear safety research CSNI
    Published date: 1 February 2017
    NEA Document
    The Safety of Long-Term Interim Storage Facilities in NEA Member Countries
    NEA/CSNI/R(2017)4

    Management of spent fuel (SF) and high-level waste (HLW) is fundamental to the fuel cycle safety. The original management strategies were established on the basis of limited interim storage periods o...

    English WGFCS Nuclear safety research CSNI Safety …
    Published date: 19 January 2017
    NEA Document
    Operating Experience Insights into Pressure Boundary Component Reliability and Integrity Management: Topical Report by the Component Operational Experience, Degradation and Ageing Programme (CODAP) Group
    NEA/CSNI/R(2017)3

    This third topical report is concerned with the effectiveness of pressure boundary component reliability and integrity management (RIM). Specifically, this report addresses operating experience insig...

    English Nuclear safety research CSNI
    Published date: 15 January 2017
    NEA Document
    State-of-the-Art Report on Molten Corium Concrete Interaction and Ex-Vessel Molten Core Coolability
    NEA/CSNI/R(2016)15

    Since 2002, the Nuclear Energy Agency (NEA) has sponsored the Melt Coolability and Concrete Interaction (MCCI) co-operative project in two phases in order to investigate ex-vessel melt coolability an...

    English WGAMA Nuclear safety research CSNI
    Published date: 1 January 2017
    NEA Document
    Probabilistic Structural Integrity of a Pressurised Water Reactor Pressure Vessel: Final Report
    NEA/CSNI/R(2016)12

    Probabilistic Structural Integrity of a Pressurised Water Reactor (PWR) Pressure Vessel (PROSIR ) was a round robin exercise with the primary objective to issue some recommendations of best practices...

    English WGIAGE Nuclear safety research CSNI
    Published date: 1 December 2016
    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
    Results of the Questionnaire on Buried and Underground Tanks and Piping
    NEA/CSNI/R(2016)11
    This report summarises the responses provided by the member organisations of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) of the Committee on the Safety of Nuclear...
    English WGIAGE Nuclear safety research CSNI
    Published date: 11 October 2016
    NEA Document
    Report on Fuel Fragmentation, Relocation and Dispersal (FFRD)
    NEA/CSNI/R(2016)16

    Since the time of the first LOCA experiments, which were largely conducted with fresh fuel, changes in the fuel design, the introduction of new cladding materials and in particular the move to high b...

    English Nuclear safety research CSNI WGFS
    Published date: 10 October 2016
    NEA Document
    Operational and Regulatory Aspects of Criticality Safety: Workshop Proceedings
    NEA/CSNI/R(2016)3

    Criticality safety is an integral component of ensuring the continued safe operation of current reactor and fuel cycle facilities, as well as addressing new and interesting challenges that are expect...

    English Criticality WGFCS Nuclear safety research CSNI Proceedings Nuclear fuel cycle …
    Published date: 31 August 2016
    NEA Document
    Event Combinations of Fire and Other Events: The Fire Incidents Records Exchange Project
    NEA/CSNI/R(2016)7
    Operating experience from nuclear installations worldwide has shown that combinations of fires and other events, in particular external and internal hazards, occur throughout their entire lifetime. ...
    English Nuclear safety research CSNI
    Published date: 27 July 2016
    NEA Document
    International Iodine Workshop: Full Proceedings
    NEA/CSNI/R(2016)5

    The workshop objectives relative to reviewing and discussing the state-of-the-art knowledge of iodine and ruthenium behaviour in NPP accidents gained through research projects and progress made in th...

    English Nuclear safety research CSNI Proceedings
    Published date: 30 May 2016
    • <<
    • <
    • 1
    • 2
    • 3
    • ...
    • >
    • 50 per page
      • 10 per page
      • 20 per page
      • 50 per page
      • 500 per 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 © 2023 OECD. All rights reserved.
    Privacy
    Terms
    • en English
    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
    K310TuN2NypV7nVH