Some reports marked with a red "R" are restricted to members of the Committee on the Safety of Nuclear Installations (CSNI). Documents that are not available may be in preparation, unreleased or restricted to members of the CSNI.
Search CSNI and CNRA documents
Reference |
Title |
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NEA/CSNI/R(2024)8 R | CSNI report CODAP Topical Report: The International Operating Experience Concerning Fire Water Piping Integrity. |
NEA/CSNI/R(2024)7 R | CSNI report Summary of Phase IV of the Component Operational Experience, Degradation and Ageing Programme (CODAP). |
NEA/CSNI/R(2024)6 R | NEA report: Status and Perspectives Advances in the analysis and management of external hazards. |
NEA/CSNI/R(2024)5 R | CSNI report Benchmark on Probabilistic Fracture Mechanics for Piping Applications (PFM Benchmark). ( Keiko) |
NEA/CSNI/R(2024)4 R | Combinations of External Hazards A Survey on Hazard and Impact Assessment and Probabilistic Safety Analysis (PSA) for Nuclear Installations |
NEA/CSNI/R(2024)3 R | CSNI report CODAP Topical Report: The International Operating Experience Concerning Fire Water Piping Integrity. (Keiko) |
NEA/CSNI/R(2024)2 R | CSNI report Summary of Phase IV of the Component Operational Experience, Degradation and Ageing Programme (CODAP). ( Keiko) |
NEA/CSNI/R(2024)1 R | CSNI R- PROBABILISTIC FRACTURE MECHANICS CODES FOR PIPING INTERNATIONAL BENCHMARKFINAL REPORT Also referenced as: CSNI 2024 Reports |
NEA/CSNI/R(2023)14 | Proceedings of the Workshop on Uncertainties in the Assessment of Natural Hazards (Excluding Earthquakes) |
NEA/CSNI/R(2023)13 | WGRISK-WGEV_Survey_Task_Report |
NEA/CSNI/R(2023)12 | Summary report ERMSAR2022 (European Review Meeting on Severe Accident Research) |
NEA/CSNI/R(2023)11 | Final report on SOCRAT (Seismic simulation of Overhead CRAne on shaking Table) international benchmark |
NEA/CSNI/R(2023)10 | Report on NEA Kappa Workshop on Earthquake Ground Motions on Rock Sites (Kappa workshop) |
NEA/CSNI/R(2023)9 | Summary of Phase VIII of the International Common-Cause Data Exchange Project |
NEA/CSNI/R(2023)8 | Lessons Learned from Common-Cause Failures of Batteries |
NEA/CSNI/R(2023)7 | Summary report for Rod Bundle Heat transfer (RBHT) Project phase I |
NEA/CSNI/R(2023)6 | Summary report for ARC-F Project (Analysis of Information from Reactor Buildings and Containment Vessels of Fukushima Daiichi Nuclear Power Station |
NEA/CSNI/R(2023)5 | IRIS (Improving Robustness Assessment Methodologies for Structures Impacted by Missiles) Phase 3: Tests description and interpretation & Round robin calculations analysis |
NEA/CSNI/R(2023)4 | Status report on fuel safety implications of extended enrichment and high reactivity/high suppression core designs |
NEA/CSNI/R(2023)3 | WGEV Report on Workshop on High Winds and Tornados - Hazard Assessment and Protection of Nuclear Installations |
NEA/CSNI/R(2023)2 | The fluid-structure interaction (FSI) benchmark based on OKBM experiments to validate coupled computational fluid dynamics (CFD) and computational structural dynamics (CSD) Calculations |
NEA/CSNI/R(2023)1 | Summary document for OECD/NEA/CSNI specialists meeting on transient thermal-hydraulics in water cooled nuclear reactors (SM-TH) |
NEA/CSNI/R(2022)12 | Guidance and Principles for initiation and conduct of Joint Safety Research Projects |
NEA/CSNI/R(2022)11 | NEA specialist workshop on reactor core and containment cooling systems, long term management and reliability (RCCS-2021) |
NEA/CSNI/R(2022)10 | Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications Revision |
NEA/CSNI/R(2022)9 | OECD-NEA Leak Rate Benchmark Final Report |
NEA/CSNI/R(2022)8 | Summary of Phase III of the Component Operational Experience, Degradation & Aging Programme |
NEA/CSNI/R(2022)7 | Preparatory Study on Analysis of Fuel Debris (PreADES) Summary Report |
NEA/CSNI/R(2022)6 | PKL4 Project Executive Summary |
NEA/CSNI/R(2022)5 | The joint IAEANEA Workshop on the current implementation status of measures to manage open phase conditions in electrical power systems of NPPs |
NEA/CSNI/R(2022)4 | Activity-4 Direct current power systems" |
NEA/CSNI/R(2022)3 | Proceedings of SAMMI-2020: OECD/NEA Specialist Workshop on Advanced Measurement Method and Instrumentation for enhancing Severe Accident Management in an NPP addressing Emergency, Stabilization and Long-term Recovery Phases |
NEA/CSNI/R(2022)2 | OECD/NEA CSNI Virtual CFD4NRS-8 Workshop |
NEA/CSNI/R(2022)1 | ICDE Topical Report: Collection and Analysis of Common Cause Pre-Initiator Human Failure Events |
NEA/CSNI/R(2021)14 | Digital I&C PSA Comparative Application of Digital I&C Modelling Approaches for PSA |
NEA/CSNI/R(2021)14/ADD | Digital I&C PSA Comparative Application of Digital I&C Modelling Approaches for PSA Volume 2: Appendices B0-B6 |
NEA/CSNI/R(2021)13 | OECD/NEA Leak-Before-Break Benchmark Phase 1 Final Report |
NEA/CSNI/R(2021)12 | MECOS - Towards New Approach for Seismic Design of Piping Systems |
NEA/CSNI/R(2021)11 | Proceedings of the 2017 International Workshop on Fuel Modelling to Support Safety and Performance Enhancement for Water-cooled Reactors |
NEA/CSNI/R(2021)10 | Benchmark on External Events Hazard Frequency and Magnitude Statistical Modelling |
NEA/CSNI/R(2021)9 | International Severe Accident Management Conference (ISAMC) |
NEA/CSNI/R(2021)8 | OECD/NEA THAI-3 Project Final Report |
NEA/CSNI/R(2021)7 | ICDE Project Report: Lessons Learned from Common-Cause Failures of Motor-Operated Valves |
NEA/CSNI/R(2021)6 | Summary Report of the ATLAS 2 Project |
NEA/CSNI/R(2021)5 | Proceedings of the International Workshop on Developments in Safety Assessment Approaches and Safety Management Practices of Fuel Cycle Facilities |
NEA/CSNI/R(2021)4 | Technical Meeting on the Management of DC Power Systems and Application of New Devices in Safety Electrical Power Systems |
NEA/CSNI/R(2021)3 | New Devices for Electrical Equipment Replacement/Retrofits and New Build |
NEA/CSNI/R(2021)2 | Status Report on Reliability of Thermal-Hydraulic Passive Systems (Addendum: PERSEO Benchmark Report) |
NEA/CSNI/R(2021)2/ADD | WGAMA PERSEO BENCHMARK RESULTS REPORT |
NEA/CSNI/R(2021)1 | Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Experiments Related to Nuclear Reactor Thermal Hydraulics and Severe Accidents (SWINTH-2019) |
NEA/CSNI/R(2020)17 | ICDE project: Common-Cause Failures of Safety and Relief Valves |
NEA/CSNI/R(2020)16 | SAPIUM: Development of a Systematic APproach for Input Uncertainty quantification of the physical Models in thermal-hydraulic codes Good Practices Guidance Report |
NEA/CSNI/R(2020)15 | ICDE project: Operational Experience on Common-Cause Failures due to External Environmental Factors |
NEA/CSNI/R(2020)14 | BIP3 Final Report |
NEA/CSNI/R(2020)13 | Joint PKL-ATLAS Workshop on Analytical Activities related to PKL4 and ATLAS2 Projects Universitat Politècnica de Catalunya Barcelona, Spain 7-9 November 2018 |
NEA/CSNI/R(2020)12 | Use of NEA Database Projects Operating Experience Data for Probabilistic Safety Assessment |
NEA/CSNI/R(2020)11 | X-FEM Final Report |
NEA/CSNI/R(2020)10 | RIA_Benchmark Phase-III Report |
NEA/CSNI/R(2020)9 | Concepts and Terminology for Protecting Nuclear Installations from Flood Hazards |
NEA/CSNI/R(2020)8 | Advancing the Robustness of Electrical Power Systems of Nuclear Power Plants |
NEA/CSNI/R(2020)7 | Cold Leg Mixing CFD UQ Benchmark Results |
NEA/CSNI/R(2020)6 | Status on Simulation Capability of 3D System-Scale Thermal-Hydraulic (T/H) Analysis Codes |
NEA/CSNI/R(2020)5 | Workshop on Experimental Validation and Application of CFD and CMFD Codes to Nuclear Reactor Safety Issues, CFD4NRS-7 |
NEA/CSNI/R(2020)4 | Proceedings of the Workshop on Source Term: A Report by the Committee on the Safety of Nuclear Installations Working Group on the Analysis and Management of Accidents |
NEA/CSNI/R(2020)3 | Requirements for CFD-Grade Experiments for Nuclear Reactor Thermal Hydraulics |
NEA/CSNI/R(2020)2 | Evaluation of design and monitoring requirements for vibrations in safety-related fluid systems |
NEA/CSNI/R(2020)1 | ICDE Topical report: Collection and Analysis of Intersystem Common Cause Failure Events |
NEA/CSNI/R(2019)16 | Status of Site-Level (including Multi-unit) PSA Developments |
NEA/CSNI/R(2019)16/ADD | Status of Site-Level (including Multi-unit) PSA Developments: Annexes B and C |
NEA/CSNI/R(2019)15 | Pre-stressed concrete reactor containment behaviour in test condition taking into account ageing effects (VeRCoRs) |
NEA/CSNI/R(2019)14 | Assessment of the Safe Shutdown Earthquake Robustness Against on Site Observations (ASSER-OSO) |
NEA/CSNI/R(2019)13 | OECD/NEA CODAP PROJECT TOPICAL REPORT: A REVIEW OF THE POST-1998 EXPERIENCE WITH THERMAL FATIGUE IN HEAVY WATER AND LIGHT WATER REACTOR PIPING COMPONENTS |
NEA/CSNI/R(2019)11 | Report on the Phase 3 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET) |
NEA/CSNI/R(2019)10 | Use and development of Probabilistic safety Assessment An Overview of the Situation at the End of 2017 |
NEA/CSNI/R(2019)9 | Proceedings of International Workshop on Chemical Hazards in Fuel Cycle Facilities Nuclear Processing |
NEA/CSNI/R(2019)9/ADD1 | Proceedings of International Workshop on Chemical Hazards in Fuel Cycle Facilities Nuclear Processing - Appendix C |
NEA/CSNI/R(2019)8 | CSNI Technical Opinion Paper No. 17 Fire Probabilistic Safety Assessments for Nuclear Power Plants: 2019 Update |
NEA/CSNI/R(2019)7 | NEA Component Operational Experience,Degradation & Ageing Programme (CODAP): Second Term (2015-2017) Status Report |
NEA/CSNI/R(2019)6 | ICDE Topical Report: Collection and Analysis of Multi-Unit Common-Cause Failure Events |
NEA/CSNI/R(2019)5 | ICDE Topical Report: Provision against Common-Cause Failures by Improving Testing |
NEA/CSNI/R(2019)4 | ICDE Topical Report: Collection and Analysis of Common-Cause Failures due to Plant Modifications |
NEA/CSNI/R(2019)3 | ICDE Project Report: Summary Phase VII of the International Common-Cause Data Exchange Project |
NEA/CSNI/R(2019)2 | Components and Structures under Severe Accident Loading (COSSAL) |
NEA/CSNI/R(2019)2/ADD1 | Components and Structures under Severe Accident Loading (COSSAL): Final Report - APPENDIX |
NEA/CSNI/R(2019)1 | Comparison of PSHA in areas with different level of seismic activity |
NEA/CSNI/R(2018)14 | Workshop Proceedings Working Group on External Events |
NEA/CSNI/R(2018)13 | Status Report on Long Term Management and Actions for a Severe Accident in a Nuclear Power Plant _ WGAMA Report |
NEA/CSNI/R(2018)12 | OECD/NEA CODAP Project Topical Report on Basic Principles of Collecting & Evaluating Operating Experience Data on Metallic Passive Components April 2018 |
NEA/CSNI/R(2018)11 | Report on OECD HYMERES Project PANDA and MISTRA Experiments |
NEA/CSNI/R(2018)10 | Report on Comparison of Methodologies for Simulation of Electrical Systems in Nuclear Power Plants |
NEA/CSNI/R(2018)9 | Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors: Proceedings of a WGFS Workshop |
NEA/CSNI/R(2018)8 | The NEA Cable Ageing Data and Knowledge Project CADAK Report on the First and Second Term (2012-2017) |
NEA/CSNI/R(2018)7 | Examination of Approaches for Screening External Hazards |
NEA/CSNI/R(2018)6 | STEM Final Summary Report |
NEA/CSNI/R(2018)5 | 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)4 | Report on the Phase 2 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET) |
NEA/CSNI/R(2018)4/ADD1 | Report on the Phase 2 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET) - APPENDIX |
NEA/CSNI/R(2018)3 | MECOS Project on Metallic Component Margins Under High Seismic Loads |
NEA/CSNI/R(2018)2 | Operating Experience Insights into Below Ground Piping - A Topical Report by the NEA Component Operational Experience, Degradation and Ageing Programme |
NEA/CSNI/R(2018)1 | Status of Practice for Level 3 Probabilistic Safety Assessment |
NEA/CSNI/R(2017)20 | Computational Fluid Dynamics for Nuclear Reactor Safety Applications-6(CFD4NRS-6) Workshop Proceedings 13-15 September 2016 Cambridge USA |
NEA/CSNI/R(2017)19 | OECD/NEA CFDUQ Benchmark Exercise: CFD prediction and Uncertainty Quantification of a GEMIX mixing layer test |
NEA/CSNI/R(2017)18 | Phenomena Identification and Ranking Table (PIRT) on Spent Fuel Pools under Loss-of-Cooling and Loss-of-Coolant Accident Conditions WGFS Report |
NEA/CSNI/R(2017)17 R | CSNI Operating Plan and Guidelines 2017-2022 |
NEA/CSNI/R(2017)17/REV1 | Operating Plan and Guidelines for the Nuclear Energy Agency Committee on the Safety of Nuclear Installations: 2017-2022 |
NEA/CSNI/R(2017)16 | Informing Severe Accident Management Guidance and Actions for Nuclear Power Plants through Analytical Simulation |
NEA/CSNI/R(2017)15 | Status Report on Ex-Vessel Steam Explosion: EVSE |
NEA/CSNI/R(2017)14 | Investigating Heat and Smoke Propagation Mechanisms in Multi-Compartment Fire Scenarios: Final Report of the PRISME Project |
NEA/CSNI/R(2017)13 | Workshop Proceedings -Working Group on External Events (WGEV) Understanding the Impact of External Hazards on Nuclear Facilities: Severe Weather and Storm Surge Paris, France, 24-26 February 2016 |
NEA/CSNI/R(2017)13/ADD1 R | Workshop Proceedings -Working Group on External Events (WGEV) Understanding the Impact of External Hazards on Nuclear Facilities: Severe Weather and Storm Surge Paris, France, 24-26 February 2016 Papers / Presentations |
NEA/CSNI/R(2017)12 | Proceedings of the CSNI Workshop on Developments in Fuel Cycle Facilities (FCFs) after the Fukushima Daiichi Nuclear Power Station (NPS) Accident Aomori City, Japan, 15-17 November 2016 |
NEA/CSNI/R(2017)12/ADD1 | APPENDIX 3 - CONFERENCE PAPERS Proceedings of the CSNI Workshop on Developments in Fuel Cycle Facilities (FCFs) after the Fukushima Daiichi Nuclear Power Station (NPS)Accident Aomori City, Japan 15-17 November 2016 |
NEA/CSNI/R(2017)11 | Benchmark Results on the Analytical Evaluation of the Fracture Mechanic Parameters K and J |
NEA/CSNI/R(2017)10 | Summary and Conclusions of the Joint PKL-3-ATLAS Workshop on Analytical Activities Lucca, Italy 13-15 April 2016 |
NEA/CSNI/R(2017)9 | Summary Report of the NEA-Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS) Joint Project |
NEA/CSNI/R(2017)8 | ICDE Project Report: ICDE Workshop - Collection and Analysis of Emergency Diesel Generator Common-Cause Failures Impacting Entire Exposed Population |
NEA/CSNI/R(2017)7 | 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)6 | Project 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/ADD R | APPENDICES |
NEA/CSNI/R(2017)5 | Probabilistic Safety Assessment Insights Relating to the Loss of Electrical Sources |
NEA/CSNI/R(2017)4 | The Safety of Long-Term Interim Storage Facilities in NEA member countries |
NEA/CSNI/R(2017)3 | 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)2 | Proceedings of the Fourth International Conference on Fatigue of Nuclear Reactor Components 28th September-1 October 2015 in Seville, Spain |
NEA/CSNI/R(2017)2/ADD1 | APPENDIX 4 - Proceedings of the 4th International Conference on Fatigue of Nuclear Reactor Components 28 September-1 October 2015 Seville, Spain |
NEA/CSNI/R(2017)1 | Reactivity-Initiated Accident (RIA) Fuel-Codes Benchmark Phase II: Uncertainty and Sensitivity Analyses |
NEA/CSNI/R(2016)19 | Safety Research Opportunities Post-Fukushima - Initial Report of the Senior Expert Group |
NEA/CSNI/R(2016)18 | Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark Final Report |
NEA/CSNI/R(2016)17 | Experts' Workshop On Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications - February 19-21, 2015 Charlotte, North Carolina (USA) |
NEA/CSNI/R(2016)17/ADD2 | Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications Proceedings of the Expert Workshop Charlotte, United States 19-21 February 2015 APPENDIX C Speaker presentations: abstracts/texts graphics |
NEA/CSNI/R(2016)17/ADD1 | Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications Proceedings of the Expert Workshop Charlotte, United States 19-21 February 2015 APPENDIX B White Papers |
NEA/CSNI/R(2016)16 | REPORT ON FUEL FRAGMENTATION, RELOCATION, DISPERSAL (FFRD) |
NEA/CSNI/R(2016)15 | State-of-the-Art Report on Molten-Corium-Concrete interaction and Ex-Vessel Molten-Core Coolability |
NEA/CSNI/R(2016)14 | Scaling in System Thermal-Hydraulics Applications to Nuclear Reactor Safety and Design: a State-of-the-Art Report. |
NEA/CSNI/R(2016)13 | Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET) |
NEA/CSNI/R(2016)13/ADD1 | Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET) APPENDICES |
NEA/CSNI/R(2016)12 | Probabilistic Structural Integrity of a Pressurised Water Reactor (PWR) Pressured Vessel - Final Report |
NEA/CSNI/R(2016)11 | Results of questionnaire on Buried and Underground Tanks and Piping |
NEA/CSNI/R(2016)10 | Final Integration Report of the Rig-of-safety Assessment (ROSA-2) Project - 2009-2012 |
NEA/CSNI/R(2016)9 | PREMIUM: A Benchmark on the Quantification of the Uncertainty of the Physical Models in the System Thermal-Hydraulic Codes - Methodologies and Data Review |
NEA/CSNI/R(2016)8 | 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)7 | OECD FIRE Report - Topical Report n°3 Event Combinations of Fires and Other Events |
NEA/CSNI/R(2016)6/VOL2 | Reactivity Initiated Accident (RIA) Fuel Codes Benchmark Phase-II Volume 2: Task No. 1 Specifications |
NEA/CSNI/R(2016)6/VOL1 | Reactivity Initiated Accident (RIA) Fuel Codes Benchmark Phase-II Volume 1: Simplified Cases Results Summary and Analysis |
NEA/CSNI/R(2016)5 | International Iodine Workshop Summary Report |
NEA/CSNI/R(2016)4 | Review of Uncertainty Methods for Computational Fluid Dynamics Application to Nuclear Reactor Thermal Hydraulics |
NEA/CSNI/R(2016)3 | Proceedings of an OECD/CSNI Workshop on Operational and Regulatory Aspects of Criticality Safety |
NEA/CSNI/R(2016)2 | The Nuclear Energy Agency/Paul Scherrer Institute Computational Fluid Dynamics Benchmark Exercise |
NEA/CSNI/R(2016)1 | Computational Fluid Dynamics for Nuclear Reactor Safety-5 (CFD4NRS-5) - Workshop Proceedings, 9-11 September 2014, Zurich, Switzerland |
NEA/CSNI/R(2015)19 | Benchmarking of Fast-running Software Tools Used to Model Releases During Nuclear Accidents |
NEA/CSNI/R(2015)18 | Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF Project) - Phase I Summary Report, March 2015 |
NEA/CSNI/R(2015)17 | ICDE Workshop on Collection and Analysis of Common-Cause Failures due to External Factors |
NEA/CSNI/R(2015)16 | Human Performance under Extreme Conditions With Respect to a Resilient Organization - Proceedings of a CSNI International Workshop, Brugg, Switzerland, 24 26 February 2014 |
NEA/CSNI/R(2015)15 | CSNI Workshop on Testing PSHA Results and Benefit of Bayesian Techniques for Seismic Hazard Assessment Pavia, Italy 4-6 February 2015 |
NEA/CSNI/R(2015)14 | FIRE Project Report: Collection and Analysis of Fire Events (2010-2013) - Extensions in the Database and Applications |
NEA/CSNI/R(2015)13 | Questionnaire on Long-Term Operation of Commercial Nuclear Power Plants |
NEA/CSNI/R(2015)12 | International Workshop on FIRE PRA Workshop Proceedings |
NEA/CSNI/R(2015)11 | Collection and Analysis of Common-Cause Failures of Heat Exchangers - International Common-cause Failure Data Exchange (ICDE) Project Report, April 2013 |
NEA/CSNI/R(2015)10 | OECD NEA CSNI WGIAGE TASK ON HIGH ENERGY ARCING FAULT EVENTS (HEAF) |
NEA/CSNI/R(2015)9 | SEISMIC INPUT DEFINITION FOR NUCLEAR FACILITIES CURRENT PRACTICES |
NEA/CSNI/R(2015)8 | Interim Report on Metallic Component Margins Under High Seismic Loads |
NEA/CSNI/R(2015)7 | OECD/NEA COMPONENT OPERATIONAL EXPERIENCE, DEGRADATION & AGEING PROGRAMME (CODAP): FIRST TERM (2011-2014) STATUS REPORT |
NEA/CSNI/R(2015)6 | CODAP TOPICAL REPORT: OPERATING EXPERIENCE INSIGHTS ON PIPE FAILURES IN ELECTRO-HYDRAULIC CONTROL & INSTRUMENT AIR SYSTEMS |
NEA/CSNI/R(2015)5 | Bonded or Unbonded Technologies for Nuclear Reactor Prestressed Concrete Containments |
NEA/CSNI/R(2015)4 | "ROBELSYS" Workshop Proceedings ROBUSTNESS OF ELECTRICAL SYSTEMS OF NPPs in Light of the Fukushima Daiichi Accident |
NEA/CSNI/R(2015)4/ADD | "ROBELSYS" Workshop Proceedings ROBUSTNESS OF ELECTRICAL SYSTEMS OF NPPs in Light of the Fukushima Daiichi Accident |
NEA/CSNI/R(2015)3 | Ability of Current Advanced Codes to Predict In-Vessel Core Melt Progression and Degraded Core Coolability - Benchmark Exercise on Three Mile Island-2 Plant - Final Report |
NEA/CSNI/R(2015)2 | Status Report on Spent Fuel Pools under Loss-of-Coolant Accident Conditions Final Report |
NEA/CSNI/R(2015)1 | Joint CSNI WGHOF/WGRISK report on Establishing Desirable Attributes of Current Human Reliability Assessment (HRA) Techniques in Nuclear Risk Assessment |
NEA/CSNI/R(2014)16 | WGRISK Task DIGREL - Failure modes taxonomy for reliability assessment of digital I&C systems for PRA |
NEA/CSNI/R(2014)15 | OECD/SERENA Project Report - Summary and Conclusions |
NEA/CSNI/R(2014)14 | Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark Phase II: Identification of Influential Parameters |
NEA/CSNI/R(2014)13 | Extension of CFD Codes Application to Two-Phase Flow Safety Problems - Phase 3 |
NEA/CSNI/R(2014)13/REV1 R | Extension of CFD Codes Application to Two-Phase Flow Safety Problems |
NEA/CSNI/R(2014)12 | Assessment of CFD Codes for Nuclear Reactor Safety Problems - revision 2 |
NEA/CSNI/R(2014)11 | Best Practice Guidelines for the use of CFD in Nuclear Reactor Safety Applications - revision |
NEA/CSNI/R(2014)10 | Leaking fuel impacts and practices |
NEA/CSNI/R(2014)9 | PSA OF NATURAL EXTERNAL HAZARDS INCLUDING EARTHQUAKE Workshop proceedings |
NEA/CSNI/R(2014)8 | Status Report on Hydrogen Management and Related Computer Codes |
NEA/CSNI/R(2014)7 | OECD/NEA/CSNI Status Report on Filtered Containment Venting |
NEA/CSNI/R(2014)6 | CODAP Topical Report:Flow Accelerated Corrosion (FAC) of Carbon Steel & Low Alloy Steel Piping in Commercial Nuclear Power Plants |
NEA/CSNI/R(2014)5 | Improving Robustness Assessment Methodologies for Structures Impacted by Missiles (IRIS_2012) Final Report |
NEA/CSNI/R(2014)5/ADD1 | Improving Robustness Assessment Methodologies for Structures Impacted by Missiles (IRIS_2012) Final Report |
NEA/CSNI/R(2014)4 | Proceedings of the CFD for Nuclear Reactor Safety Applications (CFD4NRS-4) Workshop, 10-12 September 2012, Daejeon Convention Centre (DCC), Yuseong, Daejeon, Korea |
NEA/CSNI/R(2014)3 | Containment Code Validation Matrix |
NEA/CSNI/R(2014)2 | Use of OECD Data Project Products in Probabilistic Safety Assessment |
NEA/CSNI/R(2014)1 | Proceedings of OECD/NEA WGIAGE Workshop on the Non-Destructive Evaluation of Thick-walled Concrete Structures Prague, Czech Republic 17-19 September 2013 |
NEA/CSNI/R(2013)13 R | SFP Project concluding seminar - Executive Summary, Paris, France, 22-23 October 2013 |
NEA/CSNI/R(2013)12 | Update Knowledge Base for Long-term Core Cooling Reliability |
NEA/CSNI/R(2013)12/add1 | Updated Knowledge Base for Long Term Core Cooling Reliability |
NEA/CSNI/R(2013)11/PART2 | Proceedings of the Second Workshop on Seismic Observation in Deep Boreholes and Its Application 7-9 November 2012 At the Niigata Institute of Technology, Kashiwazaki, Japan Hosted by Japan Nuclear Energy Safety Organisation |
NEA/CSNI/R(2013)11/PART1 | Proceedings of the Second Workshop on Seismic Observation in Deep Boreholes and Its Application 7-9 November 2012 at the Niigata Institute of Technology, Kashiwazaki, Japan |
NEA/CSNI/R(2013)10 | Safety of Long-term Interim Storage Facilities - Workshop Proceedings, Munich, Germany, 21-23 May 2013 |
NEA/CSNI/R(2013)9 R | Achievements of NEA safety research activities with Fukushima implications |
NEA/CSNI/R(2013)8/part1 | Barcelona Workshop Proceedings OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations, hosted by Technical University of Catalonia (UPC) with the support from Spanish Nuclear Safety Council (CSN) Barcelona, Spain, 16-18 November 2011 |
NEA/CSNI/R(2013)8/PART4 | Barcelona Workshop Proceedings OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations, hosted by Technical University of Catalonia (UPC) with the support from Spanish Nuclear Safety Council (CSN) Barcelona, Spain, 16-18 November 2011 |
NEA/CSNI/R(2013)8/PART3 | Barcelona Workshop Proceedings OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations, hosted by Technical University of Catalonia (UPC) with the support from Spanish Nuclear Safety Council (CSN) Barcelona, Spain, 16-18 November 2011 |
NEA/CSNI/R(2013)8/PART2 | Barcelona Workshop Proceedings OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations, hosted by Technical University of Catalonia (UPC) with the support from Spanish Nuclear Safety Council (CSN) Barcelona, Spain, 16-18 November 2011 |
NEA/CSNI/R(2013)7 | RIA Fuel Codes Benchmark - Volume 1 |
NEA/CSNI/R(2013)6 | OECD FIRE Project - TOPICAL REPORT No. 1 Analysis of High Energy Arcing Faults, HEAF |
NEA/CSNI/R(2013)5 | Report of the OECD/NEA-KAERI Rod Bundle CFD Benchmark Exercise |
NEA/CSNI/R(2013)4 | ICDE Project Report:Collection and Analysis of Common-Cause Failures of Control Rod Drive Assemblies |
NEA/CSNI/R(2013)3 | Proceedings of the 1st Workshop on Seismic Observation in Deep Borehole and its Applications 25-26 November 2010 Niigata Institute of Technology, Kashiwazaki, Japan |
NEA/CSNI/R(2013)2 | ICDE Project Report: Collection and Analysis of Common-Cause Failures of Centrifugal Pumps - October 2012 |
NEA/CSNI/R(2013)1 | Final Integration Report of OECD/NEA ROSA Project 2005-2009 |
NEA/CSNI/R(2012)17 | A Joint Report on PSA for New and Advanced Reactors 2012. 5 |
NEA/CSNI/R(2012)16 | OECD-NEA Piping Failure Data Exchange Project (OECD-NEA OPDE) Report |
NEA/CSNI/R(2012)15 | PSA KNOWLEDGE TRANSFER |
NEA/CSNI/R(2012)14 | OECD/NEA PRISME Project Application Report |
NEA/CSNI/R(2012)13 | Oversight and Influencing of Leadership and Management for Safety, Including Safety Culture Proceedings of NEA/IAEA Workshop,Chester, UK, September 26-28 2011 |
NEA/CSNI/R(2012)12 | Computer-Based Systems Important to Safety (COMPSIS) Project: Second Period of Operation (2008-2011) |
NEA/CSNI/R(2012)11 | Use and Development of Probabilistic Safety Assessment An Overview of the situation at the end of 2010 |
NEA/CSNI/R(2012)10 R | Joint Report on PSA for New and Advanced Reactors |
NEA/CSNI/R(2012)9 R | CSNI Technical Opinion Paper n° _ on Defence in Depth of Electrical Systems |
NEA/CSNI/R(2012)7 | CSNI Technical Opinion Paper n° 15 - Ageing Management of Fuel Cycle Facilities |
NEA/CSNI/R(2012)6/VOL3 | International Standard Problem No.50 on ATLAS Volume 3 |
NEA/CSNI/R(2012)6/VOL2 | International Standard Problem No.50 on ATLAS Volume 2 |
NEA/CSNI/R(2012)6/VOL1 | International Standard Problem No.50 on ATLAS Volume 1 |
NEA/CSNI/R(2012)5 | OECD/SETH-2 PROJECT - Investigation of key issues for the simulation of thermal-hydraulic conditions in water reactor containment - Final Summary Report |
NEA/CSNI/R(2012)4 | OECD/NEA Workshop Safety Assessment of Fuel Cycle Facilities - Regulatory Approches and Industry Perspectives |
NEA/CSNI/R(2012)3 | Nuclear Fuel Safety Criteria Technical Review (Second Edition) |
NEA/CSNI/R(2012)2 | Workshop Proceedings on PSA for New and Advanced ReactorsOECD Conference Centre, June 20 - 24, 2011 Organized by the OECD/NEA WGRISK |
NEA/CSNI/R(2012)1 | Proceedings of the OECD/NEA Workshop on Simulator Studies for HRA Purposes, Budapest, 4-6 November 2009 |
NEA/CSNI/R(2011)14 | Proceedings of the Workshop on CFD for Nuclear Reactor Safety Applications (CF4NRS-3) September 14-16, 2010, Bethesda North Marriott & Conference Center, Bethesda, MD, USA |
NEA/CSNI/R(2011)13 | CSNI Technical Opinion Papers No.14 - Justifying the Suitability of Nuclear Licensee Organisational Structures, Resources and Competencies |
NEA/CSNI/R(2011)12 | International Common Cause Failure Data Exchange Project (ICDE) Project - Updated Coding Guidelines |
NEA/CSNI/R(2011)11 | Behaviour of Iodine Project Final Summary Report |
NEA/CSNI/R(2011)10 | The OECD/NEA Studsvik Cladding Integrity Project (SCIP) Executive summary |
NEA/CSNI/R(2011)9 | ISP-49 on Hydrogen Combustion |
NEA/CSNI/R(2011)8 | Improving Robustness Assessment Methodologies for Structures Impacted by Missiles (IRIS_2010) Final Report |
NEA/CSNI/R(2011)7 | CSNI Technical Opinion Papers No.13 LOCA Criteria Basis and Test Methodology |
NEA/CSNI/R(2011)6 | NEA/IAEA Workshop on "Soil Structure Interaction (SSI) Knowledge and Effect on Seismic Assessment of NPPs Structures and Components" - Workshop Proceedings, Ottawa, Canada, 6-8 October 2010 |
NEA/CSNI/R(2011)5 | Report of the OECD/NEA - Vattenfall T-Junction Benchmark Exercise |
NEA/CSNI/R(2011)4 | BEMUSE Phase 6 Report - Status report on the area, classification of the methods, conclusions and recommendations |
NEA/CSNI/R(2011)3 | Safety Margin Assessment and Application - Final Report |
NEA/CSNI/R(2011)2 | CSNI Operating Plan |
NEA/CSNI/R(2011)2/REV1 R | CSNI Operating Plan - 2011-2016 |
NEA/CSNI/R(2011)1 | Joint CSNI/CNRA Strategic Plan - 2011-2016 |
NEA/CSNI/R(2011)1/REV1 | Joint CSNI/CNRA Strategic Plan and Mandates - 2011-2016 |
NEA/CSNI/R(2010)15 | Technical basis for commendable practices on ageing management - Final report of the Stress corrosion cracking and Cable Ageing Project (SCAP) |
NEA/CSNI/R(2010)13 | EC-JRC/OECD-NEA Benchmark Study on Risk Informed In Service Inspection Methodologies (RISMET) |
NEA/CSNI/R(2010)12 | Experimental facilities for Sodium Fast Reactor Safety Studies (TAREF) |
NEA/CSNI/R(2010)11 | Proceedings of the Workshop on in-vessel coolability, NEA Headquarters, 12-14 October 2009. |
NEA/CSNI/R(2010)10/VOL2 | Proceedings of the Workshop on Implementation of Severe Accident Management Measures, Bottstein, 26-28 October 2009. Volume 2: Presentations |
NEA/CSNI/R(2010)10/VOL1 | Proceedings of the Workshop on Implementation of Severe Accident Management Measures, Bottstein, 26-28 October 2009. Volume 1: Papers |
NEA/CSNI/R(2010)9 | Core Exit Temperature (CET) Effectiveness in Accident Management of Nuclear Power Reactor |
NEA/CSNI/R(2010)8 | Proceedings of specialists meeting on Identifying and Overcoming Barriers to Effective Consideration of Human and Organizational Factors In Event Analysis and Root Cause Analysis |
NEA/CSNI/R(2010)7 | Proceedings of the workshop on Nuclear Fuel Behaviour during Reactivity Initiated Accidents (RIA), OECD Conference Center, 9-11 September 2009 |
NEA/CSNI/R(2010)6 | Benchmarking Calculations for Halden LOCA Test Results |
NEA/CSNI/R(2010)5 | Safety Significance of Halden LOCA Test Results |
NEA/CSNI/R(2010)4 | Ageing Management of Fuel Cycle Facilities - Proceedings of the Workshop held on 5-7 October 2009, International Energy Agency Headquarters, Paris, France |
NEA/CSNI/R(2010)3 | OECD/NEA THAI Project Final Report - Hydrogen and Fission Product issues relevant for containment safety assessment under severe accident conditions |
NEA/CSNI/R(2010)2 | Extension of CFD Codes Application to Two-Phase Flow Safety Problems - Phase 2 |
NEA/CSNI/R(2010)1 | Nuclear Fuel Behaviour under Reactivity Initiated Accident (RIA) Conditions Also referenced as: NEA No 6847 |
NEA/CSNI/R(2009)19 | OECD/NEA Pipe Failure Data Exchange (OPDE) Project - (2002-2008) Status Report |
NEA/CSNI/R(2009)18 | Report on "Digital I&C Risk" |
NEA/CSNI/R(2009)17 | Report on "Low Power and Shutdown Operations Risk" |
NEA/CSNI/R(2009)16 | Report on "Probabilistic Risk Criteria and Safety Goals" |
NEA/CSNI/R(2009)15 | State-of-the-Art Report (SOAR) on Fuel Behaviour in Loss-of-Coolant Accident (LOCA) Conditions Also referenced as: NEA No. 6846 |
NEA/CSNI/R(2009)14 | Proceedings of the CNRA/CSNI International Workshop "Taking Account of Feedback on Sump Clogging", 4-5 December 2008, OECD Headquarters |
NEA/CSNI/R(2009)13 | BEMUSE Phase V Report: Uncertainty and Sensitivity Analysis of a LB-LOCA in ZION Nuclear Power Plant |
NEA/CSNI/R(2009)12 | Proceedings of the Workshop on Experiments and CFD Codes Application to Nuclear Reactor Safety (XCFD4NRS) - Grenoble, France, 10-12 September 2008 - Full presentations available at www.nea.fr/html/nsd/csni/cfd/workshops/XCFD4NRS/index.html |
NEA/CSNI/R(2009)11 | Proceedings of the Workshop on justifying the suitability of nuclear licensee organisational structure, resources and competencies - methods, approaches & good practices. Uppsala, Sweden 8-10 September 2008 |
NEA/CSNI/R(2009)10 | Defense in Depth of Electrical Systems and Grid Internation: Final DIDELSYS Task Group Report |
NEA/CSNI/R(2009)9 | Proceedings of the Workshop on Ageing Management of Thick Walled Concrete Structures, ISI, Maintenance and Repair, Instrumentation Methods and Safety Assessment in View of LTO. Prague, Czech Republic, 1-3 October 2008 |
NEA/CSNI/R(2009)8 | Task on Advanced Reactors Experimental Facilities
(TAREF) - Report on the experimental facilities
for Gas Cooled Reactor safety studies Also referenced as: NEA n°6864 |
NEA/CSNI/R(2009)7 | CSNI Technical Opinion Paper No 12 - Research Program Topics on Human Performance in New Nuclear Plant Technology Also referenced as: NEA no. 6844 |
NEA/CSNI/R(2009)6 | FIRE Project Report: Collection and Analysis of Fire Events (2002-2008) First Applications and Expected Further Developments - re-printed |
NEA/CSNI/R(2009)5 | State-Of-the-Art Report (SOAR) on Nuclear Aerosols (NARSOAR) |
NEA/CSNI/R(2009)4 | Probabilistic Safety Analysis (PSA) of other External Events than Earthquake |
NEA/CSNI/R(2009)3 | 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)2 | PROCEEDINGS of the Workshop on Risk-Informed Piping Integrity Management Madrid, Spain, 2-4 June 2008 |
NEA/CSNI/R(2009)1 | PROCEEDINGS of the Workshop on Recent Findings and Developments in Probabilistic Seismic Hazards Analysis (PSHA) Methodologies and Applications Lyon, France, 7-9 April 2008 |
NEA/CSNI/R(2008)14 | A decade of CSNI Activities in the area of Ageing OF Nuclear Power Plant concrete structures. |
NEA/CSNI/R(2008)13 | Computer-Based Systems Important to Safety (COMPSIS) Project: 3 Years of Operation (2005-2007) |
NEA/CSNI/R(2008)12 | Technical Opinion Paper n°11 - Better Nuclear Plant Maintenance: Improving Human and Organisational Performance Also referenced as: NEA Report n°6153 |
NEA/CSNI/R(2008)11 | Technical Opinion Paper n°10 - The Role of Human and Organisational Factors in Nuclear Plant Modifications Also referenced as: NEA Report n°6315 |
NEA/CSNI/R(2008)10 | Maintaining Oversight of Licensee Safety Culture - Methods and Approaches: Proceedings of CSNI/IAEA Workshop, Chester, UK, 21-23 May 2007 |
NEA/CSNI/R(2008)9 | HRA Data and Recommended Actions to Support the Collection and Exchange of HRA Data Report of WGRisk Task 2002-1, May 2008 |
NEA/CSNI/R(2008)8 | ICDE Project Report: Collection and Analysis of Common-Cause Failures of Level Measurement Components - June 2008 |
NEA/CSNI/R(2008)7 | Summary Report on OECD/NEA Seismic Workshops |
NEA/CSNI/R(2008)6/vol3 | BEMUSE PHASE IV Report: Simulation of a LB-LOCA in Zion Nuclear Power Plant - Appendices E to G |
NEA/CSNI/R(2008)6/vol2 | BEMUSE PHASE IV Report: Simulation of a LB-LOCA in Zion Nuclear Power Plant - Appendices A to D |
NEA/CSNI/R(2008)6/vol1 | BEMUSE PHASE IV Report: Simulation of a LB-LOCA in Zion Nuclear Power Plant - Main Report |
NEA/CSNI/R(2008)5 | CSNI Collective Statement on the Support Facilities for Existing and Advanced Reactors - Function of Joint OECD-NEA Projects |
NEA/CSNI/R(2008)4 R | The Role of Research in a Regulatory Context - Questionnaire & Related Responses |
NEA/CSNI/R(2008)3 | The Role of Research in a Regulatory Context (RRRC-2): Workshop Proceedings, Paris, France, 5 December 2007 |
NEA/CSNI/R(2008)2 | OECD-IAEA Paks Fuel Project Final Report |
NEA/CSNI/R(2008)1 | ICDE Project Report: Collection and Analysis of Common-Cause Failures of Switching Devices and Circuit Breakers - October 2007 |
NEA/CSNI/R(2007)18 | Proceedings of the CSNI Workshop on Structural Reliability Evaluation and Mechanical Probablistic Approaches of NPP Components |
NEA/CSNI/R(2007)17 | Differences in Approach between Nuclear and Conventional Seismic Standards with Regard to Hazard Definition |
NEA/CSNI/R(2007)16 | Recent Developments in Level 2 PSA and Severe Accident Management |
NEA/CSNI/R(2007)15 | Main Results of the MASCA-1 and MASCA-2 Projects. Integrated application Report. June 2007 |
NEA/CSNI/R(2007)14 | Proceedings of a Specialist Meeting on the Seismic Probabilistic Safety Assessment of Nuclear Facilities held on Jeju Island, Korea, 6-8 November 2006 |
NEA/CSNI/R(2007)13 | Assessment of CFD Codes for Nuclear Reactor Safety Problems |
NEA/CSNI/R(2007)12 | Use and Development of Probabilistic Safety Assessment |
NEA/CSNI/R(2007)11 | OECD/NEA Research Programme on Fuel-coolant Interaction - SERENA Steam Explosion Resolution for Nuclear Applications: Final Report |
NEA/CSNI/R(2007)10 | International Standard Problem ISP-47 on Containment Thermal Hydraulics: Final Report |
NEA/CSNI/R(2007)9 | Task Group on Safety Margins Action Plan (SMAP) Safety Margins Action Plan - Final Report |
NEA/CSNI/R(2007)8 | Proceedings of the Workshop on Future Control Station Designs and Human Performance Issues in Nuclear Power Plants - Halden, Norway 8-10 May 2006 |
NEA/CSNI/R(2007)7 | CSNI Operating Plan (2006-2009) |
NEA/CSNI/R(2007)6 | Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) |
NEA/CSNI/R(2007)5 | Best Practice Guidelines for the use of CFD in Nuclear Reactor Safety Applications |
NEA/CSNI/R(2007)4 | BEMUSE Phase III Report: Uncertainty and Sensitivity Analysis of the LOFT L2-5 Test |
NEA/CSNI/R(2007)3 | Proceedings of the Workshop on Benchmarking of CFD Codes for Application to Nuclear Reactor Safety (CFD4NRS). Garching, 5-7 September 2006. Also available at http://www.oecd-nea.org/nsd/reports/2007/nea6298-benchmarking.html Also referenced as: NEA Report 6298 |
NEA/CSNI/R(2007)2 | Procedings of the Workshop on Evaluation of Uncertainties in Relation to Severe Accidents and Level-2 Probabilistic Safety Analysis, Aix-en-Provence, 7-9 November 2005. Also available at http://www.oecd-nea.org/nsd/reports/2007/nea6053-uncertainties.html Also referenced as: NEA Report 6053 |
NEA/CSNI/R(2007)1 | State of the Art Report (SOAR) on Iodine Chemistry |
NEA/CSNI/R(2006)8 | CSNI Integrity and Ageing Working Group Survey on Primary Water Stress Corrosion Cracking (PWSCC) and Nickel-based Alloy: Final Version September 2006 |
NEA/CSNI/R(2006)7 | Proceedings of the Workshop on Better Nuclear Plant Maintenance: Improving Human and Organisational Performance, Canada 3-5 October 2005 |
NEA/CSNI/R(2006)6 | Draft Pilot Report on Approaches to the Resolution of Safety Issues |
NEA/CSNI/R(2006)5 | Review of High Burn-up RIA and LOCA Database and Criteria |
NEA/CSNI/R(2006)4 R | Not issued |
NEA/CSNI/R(2006)3 R | Not issued |
NEA/CSNI/R(2006)2 | BEMUSE Phase 2 Report: Re-Analysis of the ISP-13 Exercise, Post Test Analysis of the LOFT L2-5 Test Calculation |
NEA/CSNI/R(2006)1 | State-of-the-Art Report (SOAR) on Systematic Approaches to Safety Management |
NEA/CSNI/R(2005)11/VOL3 | Improving Low Power and Shutdown PSA Methods and Data to Permit Better Risk Comparison and Trade-off Decision Making - Responses to the COOPRA Survey |
NEA/CSNI/R(2005)11/VOL2 | Improving Low Power and Shutdown PSA Methods and Data to Permit Better Risk Comparison and Trade-off Decision Making - Responses to the WGRISK Survey |
NEA/CSNI/R(2005)11/VOL1 | Improving Low Power and Shutdown PSA Methods and Data to Permit Better Risk Comparison and Trade-off Decision Making - Summary Report |
NEA/CSNI/R(2005)10 | Safety of Modifications at Nuclear Power Plants -The role of minor modifications and human and organisational factors |
NEA/CSNI/R(2005)9 | Review of International developments and cooperation on Risk-Informed In-Service-Inspection (RI-ISI) and Non-destructive Testing (NDT) Qualification in OECD-NEA member countries |
NEA/CSNI/R(2005)8 | CSNI Integrity and Ageing Working Group Report on Thermal Cycling in LWR Components in OECD member countries |
NEA/CSNI/R(2005)7 | CSNI Workshop International Standard Problem 48 Analysis of a 1:4 Scale Pre-stressed Concrete Containment Vessel Model under Severe Accident Conditions Lyon, France 6-7 April 2005 |
NEA/CSNI/R(2005)6 R | Not issued |
NEA/CSNI/R(2005)5/VOL3 | International Standard Problem No.48 - Containment Capacity - Appendices H-L |
NEA/CSNI/R(2005)5/VOL2 | International Standard Problem No.48 - Containment Capacity - Appendices C-G |
NEA/CSNI/R(2005)5/VOL1 | International Standard Problem No.48 - Containment Capacity - Synthesis report |
NEA/CSNI/R(2005)4 | Technical Note on Lessons Drawn from Recent (2003-4) Nuclear Power Plant Operating Experience |
NEA/CSNI/R(2005)3 | Review of international developments and cooperation on Risk-Informed In-Service-Inspection (RI-ISI) and Non-destructive Testing (NDT) Qualification in OECD-NEA member countries - Responses to the questionnaire |
NEA/CSNI/R(2005)2 | FAT3D- An OECD/NEA-CEA benchmark on thermal fatigue in fluid mixing areas |
NEA/CSNI/R(2005)1 | Progress Made in the Last Fifteen Years through Analyses of the TMI-2 Accident Performed in Member Countries |
NEA/CSNI/R(2004)24 | OECD SETH Project - Final Report of the PKL Experimental Programme part (2000-2004) |
NEA/CSNI/R(2004)23 | OECD MASCA Project - Main result of the Phase 1 (2001-2004) - Integrated Report |
NEA/CSNI/R(2004)22 | Proceedings of the CSNI Workshop on "Seismic Input Motions, Incorporating Recent Geological Studies" held on 15-17 November 2004 in Tsukuba, Japan and hosted by NIED |
NEA/CSNI/R(2004)21 | EPRI: Proceedings of the 3rd International Conference on the Fatigue of Reactor Components, held on 3-6 October 2004 in Seville, Spain |
NEA/CSNI/R(2004)20 | Risk Monitors: The State of the Art Report (SOAR) in their Development and Use at Nuclear Power Plants (Produced on behalf of the IAEA and the NEA WGRISK) |
NEA/CSNI/R(2004)19 | Proceedings of the SEGFSM Topical Meeting on LOCA Fuel Issues. Argonne National Laboratory, May 25-26, 2004 |
NEA/CSNI/R(2004)18 | ISP-46 - PHEBUS FPT-1 Integral Experiment on Reactor Severe Accidents |
NEA/CSNI/R(2004)17 | Proceedings of the NEA CSNI WGOE/SEGHOF Workshop on Modifications at NPP - Operating Experience, Safety Significance and the Role of Human Factors & Organisation, Paris, OECD Headquarters, 6-8 October 2003 |
NEA/CSNI/R(2004)16 | AECL International Standard Problem ISP-41 FU/2 Follow-up exercise (Phase II): Iodine Code Comparison Exercise against CAIMAN and RTF Experiments |
NEA/CSNI/R(2004)15 R | Not issued |
NEA/CSNI/R(2004)14 R | Not issued |
NEA/CSNI/R(2004)13 R | Not issued |
NEA/CSNI/R(2004)12 | Research Efforts Related to Wire System Ageing in NEA Member Countries |
NEA/CSNI/R(2004)11 | International Standard Problem No.48 - Containment Capacity. Phase 2 Report - Results of Pressure Loading Analysis |
NEA/CSNI/R(2004)10 | Experimental Facilities for Earthquake Engineering Simulation Worldwide. Are large testing facilities for nuclear power plants design and verification at risk? |
NEA/CSNI/R(2004)9 | Proceedings of the CSNI Workshop on "International developments and cooperation on Risk-Informed In-Service-Inspection (RI-ISI) and Non-destructive Testing (NDT) Qualification" held in Stockholm, Sweden on 13-14 April 2004 and hosted by SKI. |
NEA/CSNI/R(2004)8 | Proceedings of the CSNI/RILEM Workshop on Use and Performance of Concrete in NPP Fuel Cycle Facilities - Hosted by Instituto de Ciencias de la Construcción, Eduardo Torroja, Madrid, Spain, on 15-16 March 2004 |
NEA/CSNI/R(2004)7 | SERENA co-ordinated programme (Steam Explosion Resolution for Nuclear Applications) - Phase 1 Task 1 Final Report - Identification of relevant conditions and experiments for fuel-coolant interactions in nuclear power plants - Revision 1 - December 2002 |
NEA/CSNI/R(2004)6 | Current Severe Accident Research Facilities and Projects - Revised October 2003 |
NEA/CSNI/R(2004)5 | CSNI International Standard Problem Procedures - CSNI Report N°17 - Revision 4 |
NEA/CSNI/R(2004)4 | Technical Note on the ICDE General Coding Guidelines |
NEA/CSNI/R(2004)3 | Conclusions drawn from recent (2002-2003) events in Nuclear Power Plants - Technical Note |
NEA/CSNI/R(2004)2 | Summary and Conclusions of the OECD/NRC Workshop on Debris Impact on Emergency Coolant Recirculation; Albuquerque, NM, USA, 26-27 February 2004. |
NEA/CSNI/R(2004)1 | Summary Record of the Experts meeting on the proposed OECD-IRSN STLOC Project |
NEA/CSNI/R(2003)19 | ICDE Project Report: Collection and Analysis of Common-Cause Failures of Batteries, Consejo de Seguridad Nuclear (CSN), Spain, and Nuclear Installations Inspectorate (NII), United Kingdom September 2003 |
NEA/CSNI/R(2003)18 | OECD/NEA Workshop on the Relations Between Seismological DATA and Seismic Engineering Istanbul, 16-18 October 2002 |
NEA/CSNI/R(2003)17/VOL2 | Proceedings of the Joint CSNI/CNRA Workshop on 'Redefining the Large Break LOCA: Technical Basis and its Implicationt' - Volume 2 |
NEA/CSNI/R(2003)17/VOL1 | Proceedings of the Joint CSNI/CNRA Workshop on 'Redefining the Large Break LOCA: Technical Basis and its Implicationt' - Volume 1 |
NEA/CSNI/R(2003)16 | Responses to the survey on "Redefining the Large Break LOCA: Technical Basis and its Implications" |
NEA/CSNI/R(2003)15 | ICDE Project Report: Collection and Analysis of Common-Cause Failure of Check Valves |
NEA/CSNI/R(2003)14 | Proceedings of the Workshop on Scientific Approaches to Safety Management, 8-10 April 2003 |
NEA/CSNI/R(2003)13 | Recurring Events, Volume 2. April 2003. Also referenced as: NEA/CSNI/R(99)19 |
NEA/CSNI/R(2003)12 | Answers to Remaining Quetions on Bubbler-Condenser Activity Report of the OECD NEA Bubbler-Condenser Steering Group January 2003 |
NEA/CSNI/R(2003)11 | Proceedings of the Workshop on Precursor Analysis, AVN, Brussels, Belgium, 28-30 March 2001 |
NEA/CSNI/R(2003)10 | Fuel Safety Criteria in NEA Member States |
NEA/CSNI/R(2003)9 | Ongoing and Planned Fuel Safety Research in NEA Member States -- Compiled from SEGFSM Members' Contributions, October 2002 |
NEA/CSNI/R(2003)8/VOL2 | Proceedings of the CSNI Topical Meeting on Reactivity Initiated Accidents (RIA) held in Aix-en-Provence, France on 14-15 May, 2002 |
NEA/CSNI/R(2003)8/VOL1 | Proceedings of the CSNI Topical Meeting on Reactivity Initiated Accidents (RIA) held in Aix-en-Provence, France on 14-15 May, 2002 |
NEA/CSNI/R(2003)7 | ISP-42 (PANDA tests): ISP-42-Comparison and Interpretation Report -Final Volume II (Open Exercise) |
NEA/CSNI/R(2003)6 | ISP-42 (PANDA tests): "ISP-42 - Comparison and Interpretation Report - Final" Volume I (Blind Exercise) |
NEA/CSNI/R(2003)5 | ISP-44 (KAEVER tests): "ISP-44 - Comparison and Interpretation Report - Final" |
NEA/CSNI/R(2003)4 | Topical Opinion Paper: Apparent Discrepancies Between Nuclear and Conventional Seismic Standards |
NEA/CSNI/R(2003)3 | Regulator and Industry Co-operation on Safety Research: Challenges and Opportunities -- Final Report and Answers to Questionnaire |
NEA/CSNI/R(2003)2 | Proceedings of the EPRI/USNRC/OECD International Conference on Fatigue of Reactor Components July 2002 Snowbird, Utah |
NEA/CSNI/R(2003)1 | Proceedings of the OECD Lower Head Failure Seminar 2002, hosted by the Consejo de Seguridad Nuclear, CSN Madrid, Spain 26-27 June 2002 |
NEA/CSNI/R(2002)27 | OECD Lower Head Failure Project (1999-2002) Final Project Report OECD/NRC/NERI Performed at Sandia National Laboratories |
NEA/CSNI/R(2002)26 | Technical Aspects of Ageing for Long-term Operation |
NEA/CSNI/R(2002)25 | Proceedings of the workshop "How to prevent Recurring Events more Effectively", 6-8 March 2002, Boettstein, Switzerland. |
NEA/CSNI/R(2002)24 | Conclusions drawn from recent (2001-2002) events in Nuclear Power Plants - Technical Note |
NEA/CSNI/R(2002)23 | ISP-45 (QUENCH 06 Test) - Final Comparison and Interpretation Report. |
NEA/CSNI/R(2002)22 | Lessons learnt from high magnitude earthquakes with respect to nuclear codes and standards |
NEA/CSNI/R(2002)21 | Electrochemical techniques to detect corrosion in concrete structures in nuclear installations - Technical Note |
NEA/CSNI/R(2002)20 | Workshop on the Regulatory Aspects of the Management of Change - Chester, UK, 10-12 September 2001: Summary and Conclusions |
NEA/CSNI/R(2002)19 | ICDE Project report : Collection and analysis of the common-cause failure of safety valves and relief valves |
NEA/CSNI/R(2002)18 | The Use and Development of Probabilistic Safety Assessment in NEA Member Countries |
NEA/CSNI/R(2002)17 | Procedures for the initiation, cost-sharing and management of OECD projects in nuclear safety |
NEA/CSNI/R(2002)16 | Proceedings of an exploratory meeting of experts to define an action plan on the application of computational fluid dynamics (CFD) to nuclear reactor safety problems - Aix en provence - 15-16 May 2002 |
NEA/CSNI/R(2002)15 | Proceedings of an exploratory meeting of experts to define an action plan on best estimaye calculations and uncertainty analysis - Aix en provence - 13-14 May 2002 |
NEA/CSNI/R(2002)14 | Report of the task group reviewing activities in the area of ageing of concrete structures used to construct nuclear power plant fuel-cyle facilities |
NEA/CSNI/R(2002)13 | Finite element analysis of ageing reinforced and prestressed concrete structures in nuclear power plants - An international review of current capabilities and priorities for future developments |
NEA/CSNI/R(2002)12 | Implementation of Severe Accident Management Measures - Summary and Conclusions: OECD/CSNI Workshop, 10-13 September 2001, Villigen, Switzerland |
NEA/CSNI/R(2002)11 | Severe Accident Management Operator Training and Instrumentation Capabilities, OECD/CSNI Workshop Summary and Conclusions, 12-14 March 2001, Lyon, France |
NEA/CSNI/R(2002)10 | Passive System Reliability - A Challenge to reliabillity engineering and licensing of advanced nuclear power plants - Proceedings of an international workshop hosted by the CEA 4-6 March 2002 Cadarache - France |
NEA/CSNI/R(2002)9 | Approaches to the Integration of Human Factors into the Upgrading and Refurbishment of Control Rooms - Summary and Conclusions of the Workshop, Halden, Norway, August 1999. |
NEA/CSNI/R(2002)8 | Approaches to the Integration of Human Factors into the Upgrading and Refurbishment of Control Rooms: Workshop Proceedings, Halden, Norway, 23-25 August 1999 |
NEA/CSNI/R(2002)7/VOL2 | OECD-NEA Workshop on the Evaluation of Defects, Repair Criteria & Methods of Repair for Concrete Structures in Nuclear Power Plants - Berlin 10/11 April 2002 (Volume II) |
NEA/CSNI/R(2002)7/VOL1 | OECD-NEA Workshop on the Evaluation of Defects, Repair Criteria & Methods of Repair for Concrete Structures in Nuclear Power Plants - Berlin 10/11 April 2002 (Volume I) |
NEA/CSNI/R(2002)6 | Knowledge Base for Strainer Clogging - Modifications performed in different countries since 1992 |
NEA/CSNI/R(2002)5 R | Not issued |
NEA/CSNI/R(2002)4 | Summary and conlusions of the CNRA/CSNI Workshop on Licensing and Operating Experience of Computer-Based I & C Systems - Czech Republic 25-27 September 2001 |
NEA/CSNI/R(2002)3 | Proceedings of the International Workshop Building the New HRA: Errors of Commission - From Research to Application, Rockville, Maryland, USA May 7-9 2001 Working Group on Risk Assessment (WGRisk) |
NEA/CSNI/R(2002)2 | Specialist Meeting on Safety Performance Indicators Proceedings, Madrid, Spain, October 17-19 2000 |
NEA/CSNI/R(2002)1/VOL2 | Proceedings of the CNRA/CSNI Workshop on Licensing and Operating Experience of Computer-Based I&C Systems Hluboka nad Vlatavou, Czech Republic, 25-27 September 2001 (Volume II) |
NEA/CSNI/R(2002)1/VOL1 | Proceedings of the CNRA/CSNI Workshop on Licensing and Operating Experience of Computer-Based I&C Systems, Hluboka nad Vlatavou, Czech Republic, 25-27 September 2001 (Volume I) |
NEA/CSNI/R(2001)20 | Implementation of severe Accident Management Measures - Workshop Proceedings - 10-13 September 2001 |
NEA/CSNI/R(2001)19 R | Not issued |
NEA/CSNI/R(2001)18 | Proceedings of the Topical Meeting on LOCA Fuel Safety Criteria Aix en Provence, France, 22-23 March 2001 |
NEA/CSNI/R(2001)17 | AECL International Standard Problem ISP-41 FU/1 Follow-up exercise (Phase I): Containment Iodine Computer Code Exercise Parametric Studies |
NEA/CSNI/R(2001)16 R | Not issued |
NEA/CSNI/R(2001)15 | In-Vessel and Ex-Vessel Hydrogen Sources - Report by NEA Groups of Experts |
NEA/CSNI/R(2001)14 | Technical Report on the Fatigue Crack Growth Benchmark Based on CEA Pipe Bending Tests |
NEA/CSNI/R(2001)13/VOL4 | Volume IV of the Proceedings of the OECD/NEA Workshop on the "Seismic Re-evaluation of All Nuclear Facilities", 26-27 March 2001, Ispra, Italy |
NEA/CSNI/R(2001)13/VOL3 | Volume III of the Proceedings of the OECD/NEA Workshop on the "Seismic Re-evaluation of All Nuclear Facilities", 26-27 March 2001, Ispra, Italy |
NEA/CSNI/R(2001)13/VOL2 | Volume II of the Proceedings of the OECD/NEA Workshop on the "Seismic Re-evaluation of All Nuclear Facilities", 26-27 March 2001, Ispra, Italy |
NEA/CSNI/R(2001)13/VOL1 | Volume I of the Proceedings of the OECD/NEA Workshop on the "Seismic Re-evaluation of All Nuclear Facilities", 26-27 March 2001, Ispra, Italy |
NEA/CSNI/R(2001)12 | Requalification Problems of Safety Related Equipments Following Outages - PWG1 - |
NEA/CSNI/R(2001)11 | Summary Report on the Use of Plant Safety Performance Indicators |
NEA/CSNI/R(2001)10 | ICDE Project Report on Collection and Analysis of Common-Cause Failures of Motor Operated Valves |
NEA/CSNI/R(2001)9 | OECD/CSNI Workshop on Advanced Thermal-Hydraulic & Neutronic Codes: Current & Future Applications - Summary and Conclusions, 10-13 April 2000, Barcelona, Spain |
NEA/CSNI/R(2001)8 | Proceedings of the ICDE Workshop on the qualitative and quantitative use of ICDE Data, held in Stockholm, Sweden on 12-13 June 2001 |
NEA/CSNI/R(2001)7 | Severe Accident Management (SAM) Operator Training and Instrumentation Capabilities, Workshop Proceedings, 12-14 April 2001, Lyon, France |
NEA/CSNI/R(2001)6 | Micromechanical Versus Conventional Modelling in Non-linear Fracture Mechanics |
NEA/CSNI/R(2001)5 | Status of Degraded Core Issues - Synthesis Paper, October 2000 |
NEA/CSNI/R(2001)4 | Validation Matrix for the Assessment of Thermal-Hydraulic Codes for VVER LOCA and Transients, A Report by the OECD Support Group on the VVER Thermal-Hydraulic Code Validation Matrix |
NEA/CSNI/R(2001)3 | Bubbler Condenser Related Research Work - Present Situation, by H.Karwat and H.Wolf, September 2000 |
NEA/CSNI/R(2001)2/vol2 | OECD/CSNI Workshop on Advanced Thermal-Hydraulic & Neutronic Codes: Current & Future Applications, Workshop Proceedings, 10-13 April 2000, Barcelona, Spain |
NEA/CSNI/R(2001)2/VOL1 | OECD/CSNI Workshop on Advanced Thermal-Hydraulic & Neutronic Codes: Current & Future Applications, Workshop Proceedings, 10-13 April 2000, Barcelona, Spain |
NEA/CSNI/R(2001)1 R | Not issued |
NEA/CSNI/R(2000)25 R | OECD RASPLAV Project (1994-2000) - Behaviour of the Corium molten Pool under external cooling - Final Report |
NEA/CSNI/R(2000)24 | Proceedings of the International Conference on Fatigue of Reactor Components, August 2000, Napa, California |
NEA/CSNI/R(2000)23 | CSNI/RASPLAV Seminar 2000,Summary and Conclusions, 14-15 November2000, Munich, Germany |
NEA/CSNI/R(2000)22 | ISP-43: Rapid Boron Dilution Transient Experiment, Comparison Report. File in zip format (42 mb) |
NEA/CSNI/R(2000)21 | In-Vessel Core Degradation Code Validation Matrix. |
NEA/CSNI/R(2000)20 | ICDE Project Report: Collection and Analysis of Common-Cause Failures of Emergency Diesel Generators, Idaho National Engineering and Environmental Laboratory, USA |
NEA/CSNI/R(2000)19 | Technical Notes on Ex-vessel Hydrogen Sources |
NEA/CSNI/R(2000)18 | Proceedings of the Workshop on Ex-vessel Debris Coolability, 15-18 November, 1999, Karlsruhe, Germany |
NEA/CSNI/R(2000)17 | Errors of Commission in Probabilistic Safety Assessment |
NEA/CSNI/R(2000)16 | Workshop on Update of the Knowledge Base for Sump Screen Clogging, Proceedings, May 1999, Stockholm, Sweden |
NEA/CSNI/R(2000)15 | Proceedings of the Workshop on Instrumentation & Monitoring of Concrete Structures, 22-23 March 2000, Brussels, Belgium. |
NEA/CSNI/R(2000)14 | OECD/CSNI Workshop on Ex-Vessel Debris Coolability - Summary and Recommendations, 15-18 November 1999, Karlsruhe, Germany |
NEA/CSNI/R(2000)13 | Report of the Task Group Reviewing the Activities of the Principal Working Group No.1 on Operating Experience and Human Factors (PWG1) |
NEA/CSNI/R(2000)12 | Workshop on Iodine Aspects of Severe Accident Management - Summary and Conclusions,18-20 May 1999, Vantaa, Finland |
NEA/CSNI/R(2000)10 | Carbon Monoxide - Hydrogen Combustion Characteristics in Severe Accident Containment Conditions |
NEA/CSNI/R(2000)9 | Insights into the Control of the Release of Iodine, Cesium, Strontium and other Fission Products in the Containment by Severe Accident Management. |
NEA/CSNI/R(2000)8 | Impact of Short-Term Severe Accident Management Actions in a Long-Term Perspective |
NEA/CSNI/R(2000)7 | Flame Acceleration and Deflagration-to-Detonation Transition in Nuclear Safety |
NEA/CSNI/R(2000)6/VOL2 | ISP 41 - Containment Iodine Computer Code Exercise Based on a Radioiodine Test Facility (RTF) Experiment - Appendices - |
NEA/CSNI/R(2000)6/VOL1 | ISP 41 - Containment Iodine Computer Code Exercise Based on a Radioiodine Test Facility (RTF) Experiment (Main Report) |
NEA/CSNI/R(2000)5 | CSNI International Standard Problems (ISP): Brief Descriptions (1975-1999) |
NEA/CSNI/R(2000)3 | The Strategic Plan For The Committee on the Safety of Nuclear Installations |
NEA/CSNI/R(2000)2/VOL2 | OECD/NEA Workshop on the Engineering Characterisation of Seismic Input, Proceedings, 15-17 November 1999, Brookhaven National Laboratory,Upton, New York, USA - Part. 2 |
NEA/CSNI/R(2000)2/VOL1 | OECD/NEA Workshop on the Engineering Characterisation of Seismic Input, Proceedings, 15-17 November 1999, Brookhaven National Laboratory,Upton, New York, USA - Part. 1 |
NEA/CSNI/R(2000)1 R | Not issued |
NEA/CSNI/R(1999)28 | OECD/NEA Workshop on Seismic Risk, Proceedings, 10-12 August 1999, Tokyo, Japan |
NEA/CSNI/R(1999)27 | Fire Risk Analysis, Fire Simulation, Fire Spreading and Impact of Smoke and Heat on Instrumentation Electronics - State of the Art Report (SOAR) |
NEA/CSNI/R(1999)26 | OECD/NEA Workshop on Fire Risk, Proceedings, 26 June-2 July 1999, Helsinki, Finland |
NEA/CSNI/R(1999)25 | Fuel Safety Criteria Technical Review - Results of OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria |
NEA/CSNI/R(1999)24 | Technical Opinion Paper on Fuel-Coolant Interaction |
NEA/CSNI/R(1999)23 | Degraded Core Quench : Summary of Progress 1996 -1999 |
NEA/CSNI/R(1999)22 | OECD/CSNI Seminar on Best Estimate Methods in Thermal Hydraulic Safety Analysis, Summary and Conclusions, 29 June - 1 July, 1998, Ankara, Turkey |
NEA/CSNI/R(1999)21/VOL2 | Identification and Assessment of Organisationnal Factors Related to the Safety of NPPs, Contribution from Participants and Members Countries |
NEA/CSNI/R(1999)21/VOL1 | Identification and Assessment of Organisational Factors Related to the Safety of NPPs: Vol.1 State of the Art Report (SOAR) |
NEA/CSNI/R(1999)20 | Periodic IRS Report: 1996-1999 |
NEA/CSNI/R(1999)19 | Recurring Events |
NEA/CSNI/R(1999)18 | Not issued |
NEA/CSNI/R(1999)17 | CSNI Workshop on Nuclear Power Plant Transition from Operation into Decommissioning : Human Factors and Organisation Considerations, May 17-18 1999, Rome, Italy |
NEA/CSNI/R(1999)16 | State-of-the-Art Report (SOAR) on Containment Thermalhydraulics and Hydrogen Distribution |
NEA/CSNI/R(1999)15 | State-of-the Art Report (SOAR) of Living PSA and Further Development |
NEA/CSNI/R(1999)14/REV1 | Computer-Based Systems Important to Safety (COMPSIS) Reporting Guidelines |
NEA/CSNI/R(1999)13 R | Not issued |
NEA/CSNI/R(1999)11 | Tendon Prestress Loss in NPP Containments |
NEA/CSNI/R(1999)10 | Seminar on Best Estimate Methods in Thermal Hydraulic Safety Analysis, Proceedings, 29 June -1 July 1998, Ankara, Turkey |
NEA/CSNI/R(1999)9 R | Not issued |
NEA/CSNI/R(1999)8 | Joint IAEA/NEA Workshop on Regulatory Review of Plant Safety Analysis, Proceedings, July 6-10 ,1998, Bratislava, Slovakia |
NEA/CSNI/R(1999)7 | Proceedings of the CSNI Workshop on Iodine in Severe Accident Management. Helsinki, 18-20 May 1999 |
NEA/CSNI/R(1999)6 R | Not issued |
NEA/CSNI/R(1999)5 | Specialist Meeting on Nuclear Aerosols in Reactor Safety, Summary and Conclusions, June 1998 - Full Proceedings issued as NEA/CSNI/R(1998)4 |
NEA/CSNI/R(1999)4 | ISP-40 Final Comparison & Interpretation Report |
NEA/CSNI/R(1999)3 | Comparison Report of RPV Pressurised Thermal Shock International Comparative Assessment Study (PTS ICAS) |
NEA/CSNI/R(1999)2 | ICDE Project Report on Collection & Analysis of Common Cause Failures of Centrifugal Pumps |
NEA/CSNI/R(1999)1 | Workshop on Finite Element Analysis of Degraded Concrete Structures, Proceedings, BNL, October 1998, New York, USA |
NEA/CSNI/R(1998)22 | Good Practices for User Effect Reduction |
NEA/CSNI/R(1998)21 | Workshop on In-vessel Core Debris Retention and Coolability, Summary and Conclusions, 1998, Garching, Germany |
NEA/CSNI/R(1998)20 | VVER: Specific Features Regarding Core Degradation. |
NEA/CSNI/R(1998)19 | Not issued |
NEA/CSNI/R(1998)18 | Workshop on In-vessel Core Debris Retention and Coolability, Proceedings, 1998, Garching, Germany |
NEA/CSNI/R(1998)17/VOL2 | Identification and Assessment of Organisational Factors Related to the Safety of NPPs, State-of-the Art Report (SOAR) Vol.2 |
NEA/CSNI/R(1998)17/VOL1 | Identification and Assessment of Organisational Factors Related to the Safety of NPPs: State of the Art Report (SOAR), Vol.1 |
NEA/CSNI/R(1998)16 | Workshop on Human Performance in Operational Events, Proceedings, 1997, Chattanooga, USA |
NEA/CSNI/R(1998)15 | Workshop on the Safety of Nuclear Fuel Cycle Intermediate Storage Facilities, Proceedings, 1997, Newby Bridge, Cumbria,U.K. Also referenced as: OCDE/GD(98)15 |
NEA/CSNI/R(1998)14 | Seminar on Best Estimate Methods in Thermal-hydraulic Safety Analysis, Proceedigs, 1998, Ankara, Turkey |
NEA/CSNI/R(1998)13 | Status of the Bubbler Condenser Containment System for the Reactors of the VVER-440/213 Type |
NEA/CSNI/R(1998)12 | Not issued |
NEA/CSNI/R(1998)11 | Not issued |
NEA/CSNI/R(1998)10 | International Workshop on Reliability Data Collection, Proceedings, 1998, Budapest, Hungary |
NEA/CSNI/R(1998)9 | Not issued |
NEA/CSNI/R(1998)8 | Workshop on Experience with Thermal Fatigue in LWR Piping Caused by Mixing and Stratification, Proceedings, 1998, Paris, France |
NEA/CSNI/R(1998)7 | Survey of Organic Components in Nuclear Power Plants |
NEA/CSNI/R(1998)6 | Development Priorities for Non-destructive Examination of Concrete Structures in Nuclear Plant |
NEA/CSNI/R(1998)5 | Status Report on Seismic Re-evaluation |
NEA/CSNI/R(1998)4 | Proceedings of the 3rd Specialist Meeting on Nuclear Aerosols in Reactor Safety, 15-18 June 1998, Cologne, Germany Also referenced as: GRS-166 - Summary issued as CSNI/R(1999)5 |
NEA/CSNI/R(1998)3 | Not issued |
NEA/CSNI/R(1998)2 | Not issued |
NEA/CSNI/R(1998)1 | Critical Operator Actions: Human Reliability Modeling and Data Issues: Final Task Report |
NEA/CSNI/R(1998)1/ADD1 | Critical Operator Actions: Human Reliability Modeling and Data Issues, Appendix F, Questionnaire Responses |
NEA/CSNI/R(1997)38 | ISP-38 on Bethsy test 6.9c: the final report. Vol.1 |
NEA/CSNI/R(1997)38/VOL2 | ISP-38 on Bethsy Test 6.9c Vol.2 |
NEA/CSNI/R(1997)37 | Proceedings of the 2nd CSNI Specialist Meeting on Simulators and Plant Analysers. (1997 : Espoo, Finland), 1997. |
NEA/CSNI/R(1997)36 | The Second CSNI Specialist Meeting on Simulators and Plant Analysers, Summary and Conclusions. (1997: Espoo, Finland), 1998. |
NEA/CSNI/R(1997)35 | Report on the Uncertainty Methods Study, 1998. Vol.1 |
NEA/CSNI/R(1997)35/VOL2 | Report on the Uncertainty Methods Study, 1998, Vol.2 |
NEA/CSNI/R(1997)34 | Molten material relocation into the lower plenum: a status report, 1998. |
NEA/CSNI/R(1997)33 | Proceedings of the CSNI Specialist Meeting on Advanced Instrumentation and Measurements Techniques (1997 : Santa Barbara, Calif.), 1997. Also referenced as: NUREG/CP-0160 |
NEA/CSNI/R(1997)32 | CSNI Specialist Meeting on Advanced Instrumentation and Measurements Terchniques: summary and conclusions (1997 : Santa Barbara,Calif.), 1997. |
NEA/CSNI/R(1997)31 | ISP-39 on FARO test L-14: the final report. Part1 |
NEA/CSNI/R(1997)31/PART2 | FARO test L-14 on Fuel Coolant Interaction and Quenching. Part2 |
NEA/CSNI/R(1997)30 | Specialist Meeting on Fuel Coolant Interaction: summary and conclusions (1997 : JAERI-Tokai, Japan), 1997. |
NEA/CSNI/R(1997)29 | Contribution from twenty two years of CSNI International Standard Problems. |
NEA/CSNI/R(1997)28 | Development priorities for NDE of concrete structures in nuclear plants (1997 : Risley, United Kingdom), 1998 |
NEA/CSNI/R(1997)27 | Second Specialist Meeting on operator aids for severe accident management: summary and conclusions (1997 : Lyon, France), 1997. |
NEA/CSNI/R(1997)26 | Proceedings of the OECD/CSNI Specialists Meeting on Fuel- Coolant Interactions (1997 :Tokai-Mura, Japan), 1998. Part1
Also referenced as: JAERI-Conf 97-011(Parts I&II) |
NEA/CSNI/R(1997)25 | Not issued |
NEA/CSNI/R(1997)24 | Research strategies for human performance, 1998. |
NEA/CSNI/R(1997)23 | Operating and maintenance experience with computer-based systems in nuclear power plants, 1998. |
NEA/CSNI/R(1997)22 | State-of-the-Art Report (SOAR) on the current status of methodologies for seismic PSA, Paris, 1998. |
NEA/CSNI/R(1997)21 | Integrated assessment of level-1 and level-2 PSA results for internal and external events, 1998. |
NEA/CSNI/R(1997)20 | Documentation of the treatment of level-1/level-2 interface in PSAs with emphasis on accident management actions, 1998. |
NEA/CSNI/R(1997)19 | Documentation on the use of severe accident computer codes in selected level-2 PSAs for nuclear power plants, 1998. |
NEA/CSNI/R(1997)18 | Results and insights from level-2 PSAs performed in Germany, Japan, The Netherlands; Sweden, Switzerland, the United Kingdom and the United States, 1998. |
NEA/CSNI/R(1997)17 | A Compendium of practices on safety improvements in low-power and shutdown operating modes, 1997. |
NEA/CSNI/R(1997)16 | Not issued |
NEA/CSNI/R(1997)15 | Extended Task Force on Human Factors of the PWG-1 Part 1 |
NEA/CSNI/R(1997)15/PART2 | Improving reporting and coding of human and organisational factors in event reports, 1998. part 2 |
NEA/CSNI/R(1997)14/REV1 | Summary and Conclusions of the International Seminar on the Safety Research Needs for Russian-Designed Reactors held in Tokyo, Japan, 8th-9th July 1997 |
NEA/CSNI/R(1997)13/3 | The Role of simulators in operator training. Volume 3 |
NEA/CSNI/R(1997)13/2 | The Role of simulators in operator training. Volume 2 |
NEA/CSNI/R(1997)13/1 | The Role of simulators in operator training. Volume 1 |
NEA/CSNI/R(1997)12 | Joint IAEA/NEA IRS guidelines, 1997. |
NEA/CSNI/R(1997)11 | Level 2 PSA methodology and severe accident management, 1997. Also referenced as: OCDE/GD(97)198 |
NEA/CSNI/R(1997)10 | Second OECD Specialist Meeting on Operator Aids for Severe Accident Management (SAMOA-2) : proceedings (1997 : Lyon, France), 1997. |
NEA/CSNI/R(1997)9 | Joint WANO/OECD-NEA Workshop: prestress loss in NPP containments (1997 : Poitiers, France), 1997. Also referenced as: OCDE/GD(97)225 |
NEA/CSNI/R(1997)8 | Fatigue crack growth benchmark. |
NEA/CSNI/R(1997)7 | International seminar on the safety research needs for Russian- designed reactors: material presented at the international seminar (1997 : Tokyo, Japan), 1997. |
NEA/CSNI/R(1997)6 | PSA based plant modifications and backfits, 1997. Also referenced as: OCDE/GD(97)130 |
NEA/CSNI/R(1997)5 | Latent failures of safety systems, A generic study performed by the Principal Working Group 1 on operating experience and human factors, 1997. vols 1&2 |
NEA/CSNI/R(1997)4 | Proceedings of the OECD/CSNI Workshop on transient thermal- hydraulic and neutronic codes requirements (1996 : Annapolis, Maryland), 1997. Also referenced as: OCDE/GD(98)146 |
NEA/CSNI/R(1997)3 | International standard problems (ISP): brief descriptions (1975-1997), 1997. |
NEA/CSNI/R(1997)2 | Proceedings of the Specialists' Meeting on Nuclear Fuel and Control Rods, Design Evolution and Safety Aspects (1996 : Madrid, Spain), 1998. |
NEA/CSNI/R(1997)1 | NDE Techniques capability demonstration and inspection qualification: proceedings of the Joint EC OECD IAEA Specialists Meeting (1997 : Petten, The Netherlands), 1997. Also referenced as: EUR 17354 EN |
NEA/CSNI/R(1996)27 | Implementation of hydrogen mitigation techniques during severe accidents in nuclear power plants=Mise en oeuvre des techniques de mitigation de l'hydrogene pendant les accidents graves dans les centrales nucleaires, 1997. Also referenced as: OCDE/GD(96)195 |
NEA/CSNI/R(1996)26 | International standard problem ISP37: VANAM M3 - A Multi compartment aerosol depletion test with hygroscopic aerosol material: comparison report, 1996. Also referenced as: (OCDE/GD(97)16 and (GRS-137) |
NEA/CSNI/R(1996)25 | High pressure melt ejection (HPME) and direct containment heating (DCH): State-of-the-Art Report (SOAR), 1996. Also referenced as: OCDE/GD(96)194 |
NEA/CSNI/R(1996)24 | Technical note on ex-vessel core melt debris coolability and steam explosions, 1996. |
NEA/CSNI/R(1996)23 | Transient behaviour of high burnup fuel: status report / prepared by an ad hoc group of the Principal Working Group on Coolant System Behaviour(PWG-2), 1996. Also referenced as: OCDE/GD(96)196 |
NEA/CSNI/R(1996)22 | Relevant thermal hydraulic aspects of advanced reactors design: status report, 1996. Also referenced as: OCDE/GD(97)8 |
NEA/CSNI/R(1996)21 | State of the Art Report on boiling water reactor stability (SOAR on BWRs), 1997. Also referenced as: OCDE/GD(97)13 |
NEA/CSNI/R(1996)20 | Lessons learned from OECD/CSNI ISP on small break LOCA: final report, 1997. Also referenced as: OCDE/GD(97)10 |
NEA/CSNI/R(1996)19 | CSNI Status summary on utilization of best-estimate methodology in safety analysis and licensing, 1996. Also referenced as: OCDE/GD(97)7 |
NEA/CSNI/R(1996)18 | Catalogue of generic plant states leading to core melt in PWRs: includes appendix 1: detailed description of sequences leading to core melt, 1996. Also referenced as: OCDE/GD(97)11 |
NEA/CSNI/R(1996)17 | CSNI Integral test facility validation matrix for the assessment of thermal-hydraulic codes for LWR LOCA and transients, 1996. Also referenced as: OCDE/GD(97)12 |
NEA/CSNI/R(1996)16 | Evaluation of the separate effects tests (set) validation matrix, 1997. Also referenced as: OCDE/GD(97)9 |
NEA/CSNI/R(1996)15 | Computer and compiler effects on code results: status report, 1997. Also referenced as: OCDE/GD(97)6 |
NEA/CSNI/R(1996)14 | Degraded core quench: a status report, 1996. Also referenced as: OCDE/GD(97)5 |
NEA/CSNI/R(1996)13 R | Discussion material for CSNI Meeting (1996 : Paris, France), 1996. |
NEA/CSNI/R(1996)12 | Safety research needs for Russian-designed reactors / report by an OECD Support Group, 1996. |
NEA/CSNI/R(1996)11 | Report of the task group on the seismic behaviour of structures: status report, 1997. Also referenced as: OCDE/GD(96)189 |
NEA/CSNI/R(1996)10 | Seismic shear wall ISP: NUPEC's seismic ultimate dynamic response test: comparison report, 1996. Also referenced as: OCDE/GD(96)188 |
NEA/CSNI/R(1996)9 | The Implementation of hydrogen mitigation techniques: summary and conclusions: OECD Workshop (1996 : Winnipeg, Manitoba, Canada), 1996. Also referenced as: OCDE/GD(96)193 |
NEA/CSNI/R(1996)8 | Proceedings of the OECD/NEA/CSNI Workshop on the implementation of hydrogen mitigation techniques=Compte rendu de l'atelier de l'OCDE/AEN/CSIN sur la mise en oeuvre des techniques de mitigation de l'hydrogene (1996 : Winnipeg, Wanitoba), 1997. Also referenced as: AECL-11762 |
NEA/CSNI/R(1996)7 | The Chemistry of iodine in reactor safety: summary and conclusions: OECD Workshop (1996 : Wurenlingen, Switzerland), 1996. Also referenced as: OCDE/GD(96)192 |
NEA/CSNI/R(1996)6 | The Fourth CSNI Workshop on the chemistry of iodine in reactor safety: proceedings (4th : 1996 : Wurenlingen, Switzerland), 1996. Also referenced as: PSI 97-02 |
NEA/CSNI/R(1996)5 | Statistical data on reactor scrams data for 1994, 1996. |
NEA/CSNI/R(1996)4 | Probabilistic structure integrity analysis and its relationship to deterministic analysis (1996 : Stockholm, Sweden), 1996. Also referenced as: OCDE/GD(96)124 |
NEA/CSNI/R(1996)3 | Boron reactivity transients: proceedings of a specialist meeting (1995 : State College, Pa.), 1997. Also referenced as: OCDE/GD(97)117 |
NEA/CSNI/R(1996)2 | Current evaluation of the Chernobyl reactor accident release = evaluation actuelle des rejets de l'accident de Tchernobyl, 1996. Also referenced as: OCDE/GD(96)41 |
NEA/CSNI/R(1996)1 | FALSIRE: phase II: CSNI project for Fracture Analyses of Large- Scale International Reference Experiments, 1996. See also NEA/CSNI/R(99)3 Also referenced as: OCDE/GD(96)187 |
NEA/CSNI/R(1995)28 | Summary and conclusions of the CSNI Specialist Meeting on Transient Behaviour of High Burnup Fuel (1995 : Cadarache, France), 1996. |
NEA/CSNI/R(1995)27 | Joint OECD/NEA-IAEA Symposium on Human Factors and Organisation in NPP maintenance outages: impact on safety (1995 : Stockholm, Sweden), 1995. |
NEA/CSNI/R(1995)26 | Safety of the nuclear fuel cycle: topical meeting (1994 : Cadarache, France), 1996. Also referenced as: OCDE/GD(96)18 |
NEA/CSNI/R(1995)25 | Containment bypass and leaktightness, 1995. |
NEA/CSNI/R(1995)24 | The Chernobyl reactor accident source term: development of a consensus view, 1996. Also referenced as: OCDE/GD(96)12 |
NEA/CSNI/R(1995)23 | AHMED Code comparison exercise: comparison report, 1995. |
NEA/CSNI/R(1995)23/ADD | AHMED Code comparison exercise: comparison report (revised MACRES calculations), 1996. |
NEA/CSNI/R(1995)22 | Transient behaviour of high burnup fuel: proceedings of the CSNI Specialist Meeting (1995 : Cadarache, France), 1996. Also referenced as: OCDE/GD(96)197 |
NEA/CSNI/R(1995)21 | In-vessel core degradation code validation matrix, 1996. Also referenced as: OCDE/GD(96)14 |
NEA/CSNI/R(1995)20 | International standard problem ISP36: CORA-W2 experiment on severe fuel damage for a Russian type PWR: comparison report, 1996. Also referenced as: OCDE/GD(96)19 |
NEA/CSNI/R(1995)19 | Report of the task group reviewing national and international activities in the area of ageing of nuclear power plant concrete structures, 1996. Also referenced as: OCDE/GD(96)31 |
NEA/CSNI/R(1995)18 | Leak before break in reactor piping and vessels: specialist meeting (1995: Lyons, France), 1996. Vols 1-3 Also referenced as: OCDE/GD(96)11 |
NEA/CSNI/R(1995)17 | International Workshop on Aged and Decommissioned Material Collection and Testing for Structural Integrity Purposes (1995 : Mol, Belgium), 1996. Also referenced as: OCDE/GD(96)10 |
NEA/CSNI/R(1995)16 | Summary and conclusions: Specialist Meeting on Severe Accident Management Implementation (1995 : Niantic, Conn.), 1995. |
NEA/CSNI/R(1995)15 | Fuel incident notification and analysis system (FINAS) guidelines, 1996. Also referenced as: OCDE/GD(96)9 |
NEA/CSNI/R(1995)14 | Not issued |
NEA/CSNI/R(1995)13 | Proceedings of the International Workshop on Reliability Data Collection in Support of PSA, Maintenance and Life-Assurance Programmes (1995 : Toronto, Canada), 1996. Also referenced as: OCDE/GD(96)62 |
NEA/CSNI/R(1995)12 | Not issued |
NEA/CSNI/R(1995)11 | Knowledge base for emergency core cooling system recirculation reliability, 1996. |
NEA/CSNI/R(1995)10/PART2 | Human factor related common cause failures: part 2, 1996. |
NEA/CSNI/R(1995)10/PART1 | Human factor related common cause failure: part 1, 1996. Also referenced as: OCDE/GD(96)8 |
NEA/CSNI/R(1995)9/VOL2 | Evidence of aging effects on certain safety-related components: contributions of participating countries, 1995 Vol 2 |
NEA/CSNI/R(1995)9/VOL1 | Evidence of aging effects on certain safety-related components: summary and analysis, 1995 Vol 1 |
NEA/CSNI/R(1995)8 | Not issued |
NEA/CSNI/R(1995)7 | Statistical data on reactor scrams : Data for 1993, 1995. |
NEA/CSNI/R(1995)6 | Workshop on Reactor Coolant System Leakage and Failure Probabilities (1992 : Koln, Germany), 1995. Also referenced as: OCDE/GD/(95)91 |
NEA/CSNI/R(1995)5 | Specialist Meeting on Severe Accident Management Implementation (1995: Niantic, Conn.), 1995 |
NEA/CSNI/R(1995)4 | Report on round robin activities on the calculation of crack opening behaviour and leak rates for small bore piping components, 1995. Also referenced as: OCDE/GD(95)90 |
NEA/CSNI/R(1995)3 | Proceedings of the Specialist Meeting on Selected Containment Severe Accident Management Strategies (1994 : Stockholm, Sweden), 1995. |
NEA/CSNI/R(1995)2 | Living PSA development and application in Member countries: summary of TUV Workshops held from 1988 to 1994, 1996. Also referenced as: OCDE/GD(96)24 |
NEA/CSNI/R(1995)1 | State of the Art Report (SOAR) on key fracture mechanics aspects of integrity assessment, 1996. Also referenced as: OCDE/GD(96)6 |
NEA/CSNI/R(1994)35 | User effects on the transient sytem code calculations. |
NEA/CSNI/R(1994)34 | Overview of current approaches regarding the use of water to cool a molten core in the containment in ten OECD member countries, 1994. |
NEA/CSNI/R(1994)33 | Summary and conclusions: specialist meeting on selected containment severe accident management strategies (1994 : Stockholm, Sweden), 1994. |
NEA/CSNI/R(1994)32 | Core debris cooling with flooded vessel or core-catcher heat exchange coefficients under natural convection, 1994. |
NEA/CSNI/R(1994)31 | Summary and conclusions: Workshop on Large Molten Pool Heat Transfer (1994 : Grenoble, France), 1994. |
NEA/CSNI/R(1994)30 | Short overview on the definitions and significance of the late phase fission product aerosol/vapour source, 1994. |
NEA/CSNI/R(1994)29 | Final comparison report on ISP-35: NUPEC hydrogen mixing and distribution test (TEST M-7-1), 1994. Also referenced as: OCDE/GD(95)29 |
NEA/CSNI/R(1994)28 | Specific features of cesium chemistry and physics affecting reactor accident source term predictions, 1994. Also referenced as: SKI report 94:29 |
NEA/CSNI/R(1994)27 | OECD International Standard Problem Number 34: Falcon code comparison report, 1994. |
NEA/CSNI/R(1994)26 | Specialist Meeting on Erosion and Corrosion of Nuclear Power Plant Materials (1994 : Kiev, Ukraine), 1994. Also referenced as: OCDE/GD(95)2 |
NEA/CSNI/R(1994)25 | Task 12: reliability data collection and analysis to support probabilistic safety analysis (PSA): an evaluation of questionnaire results, 1994. |
NEA/CSNI/R(1994)24/VOL II | OECD/NEA/CSNI International Standard Problem No. 33 (ISP 33): PACTEL natural circulation stepwise coolant inventory reduction experiment: Comparison report, Volume II. |
NEA/CSNI/R(1994)24/VOL I | OECD/NEA/CSNI International Standard Problem No. 33 (ISP 33): PACTEL natural circulation stepwise coolant inventory reduction experiment: Comparison report, Volume I. |
NEA/CSNI/R(1994)23 | Non-destructive examination practice and results: State of the Art Report (SOAR) and PISC III results: proceedings of the Joint CEC OECD IAEA Specialists Meeting (1994 : Petten, The Netherlands), 1994. Also referenced as: EUR 15906 EN |
NEA/CSNI/R(1994)22 | Not issued |
NEA/CSNI/R(1994)21 | Risk-based management of safety systems' availability: risk based configuration control, 1994. |
NEA/CSNI/R(1994)20/VOL2 | Report of a CSNI workshop on uncertainty analysis methods (1994 : London, England), 1994. |
NEA/CSNI/R(1994)20/VOL1 | Report of a CSNI workshop on uncertainty analysis methods (1994 : London, England), 1994. |
NEA/CSNI/R(1994)19 | International standard problems (ISP): brief descriptions (1975-1994), 1994. |
NEA/CSNI/R(1994)18 | Statistical data on reactor scrams: data for 1992, 1994. |
NEA/CSNI/R(1994)17 | Management of maintenance outages and shutdowns: summary of reports, 1994. |
NEA/CSNI/R(1994)16 | Proceedings of the Joint Specialist Meeting on Motor-Operated Valve Issues in Nuclear Power Plants (1994 : Paris, France), 1994. |
NEA/CSNI/R(1994)15 | The Use of quantitative safety guidelines in member countries, 1994. |
NEA/CSNI/R(1994)15/REV1 | The Use of quantitative safety guidelines in member countries, 1994. Revision 1 |
NEA/CSNI/R(1994)14 | Proceedings of the OECD/NEA Workshop on the Barseback Strainer Incident (1994 : Stockholm, Sweden), 1994. |
NEA/CSNI/R(1994)13/B | Generic study on reactivity related events reported through the Incident Reporting System (IRS), 1994. |
NEA/CSNI/R(1994)13/A | Specialist Meeting on Operator Aids for Severe Accident Management and training (Samoa) (1993 : Halden, Norway), 1994. |
NEA/CSNI/R(1994)12 | FALSIRE: phase 1: CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (phase 1): comparison report, 1994. See also NEA/CSNI/R(96)1 Also referenced as: NUREG/CR-5997, GRS-108 and OCDE/GD(97)24 |
NEA/CSNI/R(1994)11 | Proceedings of the Workshop on Large Molten Pool Heat Transfer (1994 : Grenoble, France), 1994. |
NEA/CSNI/R(1994)10 | Results of recent risk studies in France; Germany, Japan, Sweden and the United States: a supplemental report of NEA/CSNI/R(92)18 "State of the Art Report (SOAR) on level 1 PSA methodology", 1994. |
NEA/CSNI/R(1994)9 | Specialist Meeting on Fire Protection and Fire Protection Systems in Nuclear Power Plants: proceedings (1993 : Cologne, Germany), 1994 |
NEA/CSNI/R(1994)8 | Proceedings of the CSNI Symposium on the Safety of the Nuclear Fuel Cycle (1994 : Paris, France), 1994. |
NEA/CSNI/R(1994)7 | Non-condensible gases in boiling water reactors, 1994. |
NEA/CSNI/R(1994)6 | In-Vessel core debris cooling through external flooding of the reactor pressure vessel: situation report, 1994. |
NEA/CSNI/R(1994)5 | Survey of containment designs for new/advanced water reactors, 1994. |
NEA/CSNI/R(1994)4 | Low temperature/low pressure chemistry inside the containment, 1994. |
NEA/CSNI/R(1994)3 | Summary of important results and SCDAP/RELAP5 analysis for OECD LOFT Experiment LP-FP-2, 1994. Also referenced as: NUREG/CR-6160. EGG-2721 |
NEA/CSNI/R(1994)2 | Primary system fission product release and transport: a State-of- the-Art Report (SOAR), 1994. Also referenced as: NUREG/CR-6193. ORNL/TM-12681 |
NEA/CSNI/R(1994)1 | Specialists Meeting on Irradiation Embrittlement and Optimisation of Annealing (1993 : Paris, France), 1994. Also referenced as: OCDE/GD(97)23 |
NEA/CSNI/R(1993)19 | Task 13: Shutdown and low power safety assessment: a status report, 1993. |
NEA/CSNI/R(1993)18 | Task 3: New man-machine interfaces in nuclear power plants, 1993. |
NEA/CSNI/R(1993)18/ADD1 | Task3: New man-machine interfaces in nuclear power plants. PartII: Appendices, 1993. |
NEA/CSNI/R(1993)17 | International Standard Problem No. 31: CORA-13 Experiment on Severe Fuel Damage, 1993. Also referenced as: GRS-106. KfK 5287 |
NEA/CSNI/R(1993)16 | Not issued |
NEA/CSNI/R(1993)15 | Not issued |
NEA/CSNI/R(1993)14 | Separate effects test matrix for thermal-hydraulic code validation, Vol.1 and 2, 1994. Also referenced as: OCDE/GD(94)82, 83 |
NEA/CSNI/R(1993)13 R | Not issued. |
NEA/CSNI/R(1993)12 | Statistical data on reactor scrams: data for 1991, 1993. |
NEA/CSNI/R(1993)11 | CSNI Specialist meeting on simulators and plant analyzers (1992: Lappeenranta, Finland), 1994. |
NEA/CSNI/R(1993)10 | Management of maintenance outages and shutdowns: summary of reports, 1993. |
NEA/CSNI/R(1993)9 | Proceedings of the Specialist Meeting on Operator Aids for Severe Accidents Management and Training (1993 : Halden, Norway), 1993. |
NEA/CSNI/R(1993)8 | Proceedings of the CSNI Specialists Meeting on Fuel-Coolant Interactions (1993 : Santa Barbara, Calif.), 1994. Also referenced as: NUREG/CP-0127 |
NEA/CSNI/R(1993)7 | Physical and chemical characteristics of aerosols in the containment, 1993. |
NEA/CSNI/R(1993)6 | Effects of hydrogen combustion on fission products and aerosols, 1993. |
NEA/CSNI/R(1993)5 | Specialist meeting on core debris/concrete interactions: summary and recommendations (1992 : Karlsruhe, Germany), 1993. |
NEA/CSNI/R(1993)4 | International standard problem 29: distribution of hydrogen within the HDR containment under severe accident conditions: final comparison report, 1993. |
NEA/CSNI/R(1993)3 | Specialist Meeting on Instrumentation to Manage Severe Accidents: summary and recommendations (1992 : Cologne, Germany), 1992. |
NEA/CSNI/R(1993)2 | Hydrogen management techniques in containment, 1993. |
NEA/CSNI/R(1993)1 | Positive/negative aspects of measures designed to protect the containment, 1993. |
NEA/CSNI/R(1992)21 | Proceedings of the Joint IAEA/CSNI Specialists' Meeting on Fracture Mechanics Verification by Large-Scale Testing (1992 : Oak Ridge, Tennessee), 1993. Also referenced as: NUREG/CP-0131. ORNL/TM-12413 |
NEA/CSNI/R(1992)20/VOL2 | ISP-27: OECD/NEA/CSNI International Standard Problem N? 27: Bethsy experiment 9.1B 2" cold leg break without HPSI and with delayed ultimate procedure: comparison report, 1992. |
NEA/CSNI/R(1992)20/VOL1 | ISP-27: OECD/NEA/CSNI International Standard Problem N? 27: Bethsy experiment 9.1B 2" cold leg break without HPSI and with delayed ultimate procedure: comparison report, 1992. |
NEA/CSNI/R(1992)19 | Probabilistic safety assessment of LWR containment systems performance, 1992. |
NEA/CSNI/R(1992)18 | State of the Art Report (SOAR) on level-1 PSA methodology, 1992. |
NEA/CSNI/R(1992)17/VOL2 | Phebus-SFD B9+ Experiment on the Degradation of a PWR type Core, 1992. |
NEA/CSNI/R(1992)17/VOL1 | Phebus-SFD B9+ Experiment on the Degradation of a PWR type Core, 1992. |
NEA/CSNI/R(1992)16 | PSA application to technical specifications, 1992. |
NEA/CSNI/R(1992)15 | Not issued |
NEA/CSNI/R(1992)14 | Not issued |
NEA/CSNI/R(1992)13 | Not issued |
NEA/CSNI/R(1992)12 | Proceedings of the CSNI Specialist Meeting on Transient Two-Phase Flow: Current Issues in System Thermal Hydraulics (1992 : Aix-en-Provence, France), 1992. |
NEA/CSNI/R(1992)11 | Proceedings of the 1st OECD (NEA) CSNI-Specialist Meeting on Instrumentation to Manage Severe Accidents (1992 : Cologne, FRG), 1992. Also referenced as: GRS-93 |
NEA/CSNI/R(1992)10 | Proceedings of the Second OECD (NEA) CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions (2nd : 1992 : Karlsruhe,Germany), 1992. Also referenced as: KfK 5108 |
NEA/CSNI/R(1992)9 | International standard problem ISP 30: BETA V5.1 experiment on melt-concrete interaction: comparison report, 1994. |
NEA/CSNI/R(1992)8 | Statistical data on reactor scrams: data for 1990, 1992. |
NEA/CSNI/R(1992)7 | Evaluation of post-test analyses of OECD-CSNI International Standard Problem 22, 1992. |
NEA/CSNI/R(1992)6 | Specialist Meeting on Severe Accident Management Programme Development: summary and conclusions (1991 : Rome, Italy), 1992. |
NEA/CSNI/R(1992)5 | Workshop on Iodine Chemistry in Reactor Safety: summary and conclusions (1991 : Tokai-mura, Japan), 1992. |
NEA/CSNI/R(1992)4 | Instrumentation for accident management in containment: a preliminary technical document, 1992. |
NEA/CSNI/R(1992)3 | A State-of-the-Art Report (SOAR) on flame acceleration and transition to detonation in hydrogen/air diluent mixtures, 1992. |
NEA/CSNI/R(1992)2 | Source term uncertainties: recent developments in understanding fission product behaviour, 1992. |
NEA/CSNI/R(1992)1 | Workshop on aerosol behaviour and thermal-hydraulics in the containment, Fontenay-aux-Roses, 1990: technical summary. Full Proceedings issued as CSNI Report n° 176 |
NEA/CSNI/R(1991)17 | NEA/CSNI-UNIPEDE Specialist Meeting on Operating Experience with Steam Generators (1991 : Brussels, Belgium), 1991. |
NEA/CSNI/R(1991)16 | Proceedings of the Specialist Meeting on Severe Accident Management Programme Development (1991 : Rome, Italy), 1992. |
NEA/CSNI/R(1991)15 | Proceedings of the Third CSNI Workshop on Iodine Chemistry in Reactor Safety (1991 : Tokai-mura, Japan), 1992. Also referenced as: JAERI-M 92-012 |
NEA/CSNI/R(1991)14 | The Complementary roles of fracture mechanics and non-destructive examination in the safety assessment of components: proceedings of a Workshop (1988 : Wuerenlingen, Switzerland), 1991. Also referenced as: OCDE/GD(97)25 |
NEA/CSNI/R(1991)13 | OECD/NEA/CSNI International standard problem no. 26 (ISP-26): ROSA-IV LSTF cold-leg small-break LOCA experiment: comparison report, 1992. |
NEA/CSNI/R(1991)12 | In-vessel core degradation in LWR severe accidents: a State of the Art Report (SOAR), 1991. |
NEA/CSNI/R(1991)11 | ISP 25 comparison report, 1991. Also referenced as: AEA-TRS-1043 |
NEA/CSNI/R(1991)10 | CSNI Specialist Meeting on safety and risk assessment in fuel cycle facilities (1991 : Tokyo, Japan), 1991. |
NEA/CSNI/R(1991)9/VOL2 | TMI-2 examination results from the OECD-CSNI program: informal report, 1991, Volume II. |
NEA/CSNI/R(1991)9/VOL1 | TMI-2 examination results from the OECD-CSNI program: informal report, 1991, Volume I. Also referenced as: EGG-OECD-9168 |
NEA/CSNI/R(1991)8 | TMI-2 Analysis exercise final report, 1992. |
NEA/CSNI/R(1991)8/B | Statistical data on reactor scrams: data for 1989, 1991. |
NEA/CSNI/R(1991)7 | Regulatory practices on pressurized thermal shock: results of an international survey, 1991. |
NEA/CSNI/R(1991)6 | International practices for analyzing, regulating and improving human performance of maintenance activities at nuclear power plants, 1991. |
NEA/CSNI/R(1991)5 | Status of PSA programmes in member countries: a compilation of contributions from members of Principal Working Group N? 5, 1991. |
NEA/CSNI/R(1991)4 | Specialist meeting on pump performance and reliability: meeting proceedings (1990 : Cologne, Germany), 1991. |
NEA/CSNI/R(1991)3 | Current national source term positions and practices in OECD member countries, 1990. |
NEA/CSNI/R(1991)2 | CSNI Workshop on PSA applications and limitations: final report to CSNI (1990 : Santa Fe, New Mexico), 1991. |
NEA/CSNI/R(1991)1 | Summary report for the second TUV-Workshop proceedings on living PSA application, 1991. |
NEA/CSNI-181 | An Account of the OECD LOFT Project - May 1990 Also referenced as: LOFT-T-3907 |
NEA/CSNI-180 | Analysis of incidents involving cognitive error and erroneous human actions, 1990. |
NEA/CSNI-179 | Inadequate isolation of containment openings and penetrations, 1990. |
NEA/CSNI-178 | International workshop on boiling water reactor stability: proceedings (1990 : Holtsville, New York), 1990. |
NEA/CSNI-177 | Consideration of quantitative safety guidelines in member countries, 1990. |
NEA/CSNI-176 | Workshop on aerosol behaviour and thermal-hydraulics in the containment: proceedings (1990 : Fontenay-aux-Roses, France), 1990. |
NEA/CSNI-175 | Proceedings of the CSNI Workshop on PSA Applications and Limitations. Santa-Fe, New Mexico, September 4-6, 1990 |
NEA/CSNI-174/vol4 | Final comparison report for international standard problem N° 22 (SPES), 1990. Vol. 4 |
NEA/CSNI-174/vol3 | Final comparison report for international standard problem N° 22 (SPES), 1990. Vol. 3 |
NEA/CSNI-174/vol2 | Final comparison report for international standard problem N° 22 (SPES), 1990. Vol. 2 |
NEA/CSNI-174/vol1 | Final comparison report for international standard problem N° 22 (SPES), 1990. Vol. 1 |
NEA/CSNI-172 | Status of PSA programmes in member countries, 1989. |
NEA/CSNI-171 | Report on the use of probabilistic safety assessment for nuclear power plant safety management: utilities' reply to a questionnaire, 1989. |
NEA/CSNI-170 | Human reliability in probabilistic risk assessments: use of operating experience, 1989. |
NEA/CSNI-169 R | Missing |
NEA/CSNI-168 R | Generic study of events involving loss of residual heat removal function: potential loss of RHR function on PWRs, 1989. |
NEA/CSNI-167 | Emergency response assisting systems (ERAS), 1989. |
NEA/CSNI-166 | Containments for pressurized water reactors: a State-of-the-Art-Report (SOAR), 1989. |
NEA/CSNI-165 | Source term mitigation aspects of accident management, 1989. |
NEA/CSNI-164/vol.b | Benchmark exercise on the chemical modelling of the release of radionuclides due to core-concrete interactions, 1989. Vol. B |
NEA/CSNI-164/vol.a | Benchmark exercise on the chemical modelling of the release of radionuclides due to core-concrete interactions, 1989. Vol. A |
NEA/CSNI-163 | Note on the outcome of the June 1989 CSNI Specialist Meeting on intentional coolant system depressurisation (1989 : Garching, Germany), 1989. |
NEA/CSNI-162/vol2 | Comparison report of the OECD/CSNI International Standard Problem 21 (Piper-one experiment PO-SB-7), 1989. |
NEA/CSNI-162/vol1 | Comparison report of the OECD/CSNI International Standard Problem 21 (Piper-one experiment PO-SB-7), 1989. |
NEA/CSNI-161 | Thermohydraulics of emergency core cooling in light water reactors: a State of the Art Report (SOAR), 1989. |
NEA/CSNI-160/vol2 | International standard problem: ISP 23: "rupture of a large diameter pipe within the HDR-containment": final comparison report, 1989. Vol. 2 |
NEA/CSNI-160/vol1 | International standard problem: ISP 23: "rupture of a large diameter pipe within the HDR-containment": final comparison report, 1989. Vol. 1 |
NEA/CSNI-159 | Proceedings of the OECD/CSNI-CEC Specialist Meeting on Trend and Pattern Analyses of Operational Data from Nuclear Power Plants (1989 : Rome, Italy). Also referenced as: EUR 12578 N |
NEA/CSNI-158 | Proceedings specialist meeting on intentional coolant system depressurization (1989 : Garching, Germany), 1989. |
NEA/CSNI-157 | Systematic collection of statistical data on reactor scrams, 1989. |
NEA/CSNI-155/vol2 | International standard problem N° 24: ISP-24: SURC-4 experiment on core-concrete interactions, 1988. Vol. 2 |
NEA/CSNI-155/vol1 | International standard problem N° 24: ISP-24: SURC-4 experiment on core-concrete interactions, 1988. Vol. 1 |
NEA/CSNI-153 | Report of task group on ex-vessel thermal-hydraulics: status of direct containment heating in CSNI member countries, 1989. |
NEA/CSNI-149 | Proceedings of the CSNI workshop on iodine chemistry in reactor safety (2nd : 1988 : Toronto), 1989. Also referenced as: AECL-9923 |
NEA/CSNI-173 | Systematic collection of statistical data on reactor scrams, 1988. |
NEA/CSNI-156 | Filtered containment venting systems : note on the outcome of the specialists' meeting on filtered containment venting systems (1988 : Paris, France), 1988. |
NEA/CSNI-154 | International standard problem-20 : steam generator tube rupture : nuclear power plant Doel 2 : Belgium : final report, 1988. |
NEA/CSNI-151 | Generic study on the events reported through the NEA/IRS and involving a loss of containment functions, 1988. |
NEA/CSNI-150 | Use of digital computers in the control rooms of OECD member countries, 1988. |
NEA/CSNI-148 | Specialist meeting on filtered containment venting systems : proceedings (1988 : Paris, France), 1988. |
NEA/CSNI-147 | Systematic collection of statistical data on reactor scrams, April 1988. |
NEA/CSNI-146 R | NEA/CSNI-UNIPEDE specialist meeting on regulatory and life-limiting aspects of core internals and pressure vessels (1987 : Stockholm, Sweden), 1988. |
NEA/CSNI-145/vol2 | Joint OECD/NEA/CEC Workshop on recent advances in reactor accident consequence assessment : proceedings of the first part of the workshop (1988 : Rome, Italy ), 1988. Vol. 2 |
NEA/CSNI-145/vol1 | Joint OECD/NEA/CEC Workshop on recent advances in reactor accident consequence assessment : proceedings of the first part of the workshop (1988 : Rome, Italy ), 1988. Vol. 1 |
NEA/CSNI-144 | The relevance of the Chernobyl accident to source terms for severe accidents in water-cooled and moderated reactors of western design, 1988. |
NEA/CSNI-142 | The role of human intervention in the prevention and mitigation of severe accidents : tabular comparison of the approaches taken by various member countries, 1988. |
NEA/CSNI-140 | Compendium and comparison of international practice for plugging, repair and inspection of steam generator tubing, 1988. Also referenced as: NUREG/CR-5016.PNL-6341 |
NEA/CSNI-116/ADD | Comparison of the physical models and numerical methods in the codes used for the GREST LWR code comparison exercise, 1988. Addendum |
NEA/CSNI-152 | Proceedings NEA/CSNI-UNIPEDE specialist meeting on improving technical specifications for nuclear power plants (1987: Madrid, Spain), 1987. |
NEA/CSNI-143 | Report of Task Group on Ex-Vessel Thermal-Hydraulics Corium/Concrete Interactions and Combustible Gas Distribution in Large Dry Containments, 1987. |
NEA/CSNI-141 | Environment sensitive cracking in pressure boundary materials of light water reactors, 1987. |
NEA/CSNI-139 | Pathway parameter evaluation : a survey, 1987. |
NEA/CSNI-138 | CSNI specialist meeting on training of nuclear reactor personnel : proceedings (1987 : Orlando, Fla.), 1987. Also referenced as: NUREG/CP-0089 |
NEA/CSNI-137 | Analysis of incidents involving human factors, 1987. |
NEA/CSNI-136 | Selected source term topics, 1987. |
NEA/CSNI-135 | Source term assessement, containment atmosphere control systems, and accident consequences, 1987. |
NEA/CSNI-133 | International standard problem no. 18 : ISP-18 : LOBI-MOD2 small break LOCA experiment A2-81 : final comparison report, 1987. |
NEA/CSNI-132 | CSNI code validation matrix of thermo-hydraulic codes for LWR LOCA and transients, 1987. |
NEA/CSNI-131 | International standard problem ISP-19 : behavior of a fuel rod bundle during a large break LOCA transient with a two peaks temperature history (PHEBUS experiment) : final comparison report, 1987. |
NEA/CSNI-130 | Round robin test programmes in the reliability of thick section ultrasonic inspections : State of the Art Report (SOAR), 1987. |
NEA/CSNI-134 | Comparison of regulations and licensing procedures for fuel cycle facilities particularly with regard to external hazards : proceedings of a specialists' meeting (1986 : Salamanca, Spain), 1986. |
NEA/CSNI-129 | PWR fuel behaviour in design basis accident conditions : the deformation, oxidation and embrittlement of PWR fuel cladding in a loss-of-colant accident : a State-of-the-Art Report (SOAR), 1986. |
NEA/CSNI-128 | Approaches to training programmes in NEA member countries, 1986. |
NEA/CSNI-127/vol2 | Loss of safety system functions: pilot examination of generic safety questions, 1986. vol. 2 |
NEA/CSNI-127/vol1 | Loss of safety system functions: pilot examination of generic safety questions, 1986. Vol. 1 |
NEA/CSNI-126 | Pressure suppression system containments : a State-of-the-Art Report (SOAR), 1986. |
NEA/CSNI-125 | Proceedings of the CSNI workshop on probabilistic safety assessment as an aid to nuclear power plant management (1986 : Brighton, U.K.), 1986. |
NEA/CSNI-124 | A survey of the applications made of the results of probabilistic safety analyses of nuclear power plants, 1986. |
NEA/CSNI-123 | A critical review of analytical techniques for risk studies in nuclear power stations : final report of Task 1 of CSNI Principal Working Group no. 5, 1986. |
NEA/CSNI-122 R | ISP-19 (PHEBUS/Test 218) Also referenced as: CSNI-131 (1987) |
NEA/CSNI-121 | Evaluation of the PISC-II trials results. - Final issue, 1986. Also referenced as: PISCII Report No.5.S.P./I.07.C1.86.62 |
NEA/CSNI-120 | Analysis scheme of the PISC-II trials results, 1986. Also referenced as: S.P./I.07.C1.86.61 |
NEA/CSNI-119 | Destructive examination of the PISC-II RRT plates. - Final issue, 1986. Also referenced as: PISCII Report No.3.S.P./1.07.C1.86.54 |
NEA/CSNI-119/App9 | Detailed illustration of the defects present in Plate No. 3 Italy, 1986. Also referenced as: S.P./I.07.C1.86.60 |
NEA/CSNI-119/App8 | Detailed illustration of the defects present in Plate No. 9, 1986. Also referenced as: S.P./I.07.C1.86.59 |
NEA/CSNI-119/App7 | Detailed illustration of the defects present in Plate No. 2, 1986. Also referenced as: S.P./I.07.C1.86.58 |
NEA/CSNI-119/App6 | Detailed illustration of the defects present in Plate No. 1, 1986. Also referenced as: S.P./I.07.C1.86.57 |
NEA/CSNI-119/App5 | Detailed metrology of the PISC II nozzle plate No. 3, 1986. Also referenced as: S.P./1.07.C1.86.5 |
NEA/CSNI-119/App1-4 | X-Ray examination of the PISC II RRT plates before destructive examination, 1986. Also referenced as: S.P./1.07.C1.86.55 |
NEA/CSNI-118 | The Round robin test of the PISC-II programme: plates and ultrasonic procedures used. - final issue, 1986. Also referenced as: PISCII Report N?.2.S.P./I.07.C1.86.52 |
NEA/CSNI-118/App | Procedures and techniques used for the inspection of the PISC II plates and nozzles, 1986 Also referenced as: S.P./I.07.C1.86.53 |
NEA/CSNI-117 | A Summary of the PISC-II project. - Final issue, 1986. Also referenced as: PISCII Report No.1.S.P./I.07.C1.86.51 |
NEA/CSNI-116 | Results of the GREST code comparison exercise : Benchmark problems: nos 1,2,3-A and 3-B : US PWR - Surry Unit 1 : AB sequence and S2CD sequence : German PWR - BIBLIS : LOCA sequence, 1986. |
NEA/CSNI-115/vol2 | Continuous surveillance of reactor coolant circuit integrity : proceedings of a CSNI specialist meeting = Surveillance en continu de l'integrite du circuit de refroidissement des reacteurs, 1986. |
NEA/CSNI-115/vol1 | Proceedings CSNI specialist meeting on operating experience relating to on-site electric power sources (1985 : London, England), 1986. |
NEA/CSNI-114 | Proceedings of the specialists' workshop on iodine chemistry in reactor safety, September 11-12, 1985, Harwell, England |
NEA/CSNI-113 | Stable crack growth during overstressing or proof testing of pressure vessels, 1985. |
NEA/CSNI-112/vol2 | International standard problem ISP 16 : rupture of a steam line within the HDR-containment leading to an early two-phase-flow : results of post-test analyses (Appendix IV) : final comparison report, 1985. |
NEA/CSNI-112/vol1 | International standard problem ISP 16 : rupture of a steam line within the HDR-containment leading to an early two-phase-flow : results of post-test analyses : final comparison report, 1985. |
NEA/CSNI-111 | Near-surface non-destructive examination of reactor steels : a State-of-the-Art Report (SOAR), 1985. |
NEA/CSNI-110 R | Missing |
NEA/CSNI-109 R | Missing |
NEA/CSNI-108 R | Missing |
NEA/CSNI-107 R | Missing |
NEA/CSNI-106 R | Missing |
NEA/CSNI-105 | Proceedings of the CSNI workshop on ductile fracture test methods (2nd : 1985 : Paris, France), 1985. Also referenced as: NUREG/CP-0064. MEA-2313 |
NEA/CSNI-104 | The March 1985 revision of the specification for the digital recording of ultrasonic signals, 1985. |
NEA/CSNI-102 R | Missing |
NEA/CSNI-99 R | Missing |
NEA/CSNI-98 | International Standard problem ISP 14 : behaviour of a fuel bundle simulator during a specified heatup and flooding period (Rebeka experiment) : results of post-test analyses : final comparison report, 1985. |
NEA/CSNI-95 | Proceedings of the CSNI Specialist Meeting on nuclear aerosols in reactor safety (1984 : Karlsruhe, Germany), 1985. Also referenced as: KfK 3800 |
NEA/CSNI-94 | The ultrasonic inspection of austenitic materials : State of the Art Report (SOAR), 1985. Also referenced as: ND-R-1201(R) |
NEA/CSNI-92 R | Missing |
NEA/CSNI-91/Vol2 | Proceedings NEA/CSNI - UNIPEDE Specialist Meeting on steam generators (1984 : Stockholm, Sweden), 1985. Volume 2 |
NEA/CSNI-91/Vol1 | Proceedings NEA/CSNI - UNIPEDE Specialist Meeting on steam generators (1984 : Stockholm, Sweden), 1985. Volume 1. |
NEA/CSNI-90 | Reactor noise : SMORN IV : proceedings of the Fourth Specialists Meeting on Reactor Noise, Dijon, France, 15-19 October 1984, 1985. Also referenced as: NEACRP-L-282. Progress in nuclear energy;v.15 |
NEA/CSNI-88 | Expert judgement of human reliability, 1985. |
NEA/CSNI-87 | Catalogue of test specimens for non-destructive examination, 1985. |
NEA/CSNI-86 R | Missing |
NEA/CSNI-84 R | Missing |
NEA/CSNI-81 | Design and implementation of emergency operating procedures, 1985. |
NEA/CSNI-103 | Preliminary comparison report for ISP N. 17 - An international containment standard problem based on the Marviken full scale experiment blowdown n° 18. |
NEA/CSNI-97 | Proceedings of the CSNI/NRC workshop on ductile piping fracture mechanics (1984 : San Antonio, Texas), 1984. Also referenced as: NUREG/CP-0075 |
NEA/CSNI-89 | Identifying significant human actions in reactor accidents, 1984. |
NEA/CSNI-82 | Proceedings of the CSNI specialist meeting on leak-before-break in nuclear reactor piping (1983 : Monterey, Calif.), 1984. Also referenced as: NUREG/CP-0051 |
NEA/CSNI-78 | Standard problem exercise on criticality codes for large arrays of packages of fissile materials, 1984. |
NEA/CSNI-101 | International Standard Problem N° 13 (LOFT Experiment L2-5) - Preliminary Comparison Report |
NEA/CSNI-93/vol2 | Proceedings of the OECD/CSNI specialist meeting on water reactor containment safety (October 17-21, Toronto, Ont.), 1983. Vol. 2 |
NEA/CSNI-93/vol1 | Proceedings of the OECD/CSNI specialist meeting on water reactor containment safety (October 17-21, Toronto, Ont.), 1983. Vol 1 |
NEA/CSNI-83 | Proceedings of the CSNI specialist meeting on interaction of fire and explosion with ventilation systems in nuclear facilities, 1983. |
NEA/CSNI-80 | Decay heat removal systems: proceedings of the CSNI Specialist Meeting (1983 : Wurenlingen, Switzerland), 1983. |
NEA/CSNI-79 R | Missing |
NEA/CSNI-77 | Comparison report on containment analysis standard problem N. 3, 1983. |
NEA/CSNI-76 | Second CSNI Specialist Meeting on Probabilistic Methods in Seismic Risk Assessment for Nuclear Power Plants: proceedings (2nd : 1983 : Livermore, California), 1983. Also referenced as: CONF-8305220 |
NEA/CSNI-75 | Assessing human reliability in nuclear power plants, 1983. |
NEA/CSNI-75/A.vol2 | Proceedings of a specialist meeting on defect detection and sizing, Ispra, 3-6 May 1983. Vol. 2 Also referenced as: EUR 9066 2 |
NEA/CSNI-75/A.vol1 | Proceedings of a specialist meeting on defect detection and sizing, Ispra, 3-6 May 1983. Vol. 1. Also referenced as: EUR 9066 1 |
NEA/CSNI-69 | Status of LMFBR safety technology: improving the performance and reliability of protection and shutdown systems, 1983. |
NEA/CSNI-100 | Comparison report for CSNI international standard problem 12 (ROSA-III RUN 912), 1982. Also referenced as: JAERI-M 82-120 |
NEA/CSNI-74 | Steam explosions and reactor safety, 1982. |
NEA/CSNI-73 | Some thermal-hydraulic considerations in the calculations of loads in a pressurized water reactor containment during a LOCA or MSLB, 1982. |
NEA/CSNI-72 | Gap conductance in Zircaloy-clad LWR fuel rods, 1982. |
NEA/CSNI-71 | Standard problem exercise on criticality codes for spent LWR fuel transport containers / by a CSNI Group of Experts on Nuclear Criticality Safety, 1982. |
NEA/CSNI-70 | Reactor noise : SMORN III : proceedings of the Third Specialists Meeting on Reactor Noise, Tokyo, Japan, 26-30 October 1981, 1982. Also referenced as: NEACRP-A-494. Progress in nuclear energy;v.9 |
NEA/CSNI-65 | Comparison Report on OECD/CSNI Containment Standard Problem N° 2 (Water line rupture in a branched containment chain) |
NEA/CSNI-63/Vol2 | Proceedings CSNI specialist meeting on operator training and qualifications (12-15 October 1981 : Charlotte, N.C., USA), 1982. Volume 2. Also referenced as: NUREG/CP-0031 Vol. 2 |
NEA/CSNI-63/Vol1 | Proceedings CSNI specialist meeting on operator training and qualifications (12-15 October 1981 : Charlotte, N.C., USA), 1982. Volume 1. Also referenced as: NUREG/CP-0031 Vol. 1 |
NEA/CSNI-68 | A Guide to writing maintenance test and calibration procedures by a CSNI Group of Experts on Human Error Assessment, 1981. |
NEA/CSNI-67 | Proceedings CSNI specialist meeting on instrumented precracked charpy testing, 1981. Also referenced as: EPRI NP-2102-LD. ResearchProject 1757-1 |
NEA/CSNI-66 | International standard problem 9 (LOFT Test L3-1): preliminary comparison report, 1981. Also referenced as: EGG-CAAD-5432 |
NEA/CSNI-64 | Comparison report on OECD-CSNI LOCA standard problem N? 10: refill and reflood experiment in a simulated PWR primary system (PKL), 1981. |
NEA/CSNI-62 | Status of LMFBR safety technology: reactivity monitoring in an LMFBR at shutdown, 1981. |
NEA/CSNI-61 R | Missing |
NEA/CSNI-60 | Safety aspects of fuel behaviour in off-normal and accident conditions : proceedings of a CSNI Specialist Meeting, Espoo, Finland, 1-4 September 1980, 1981. |
NEA/CSNI-59 R | Missing |
NEA/CSNI-58 R | Missing |
NEA/CSNI-57 R | Missing |
NEA/CSNI-56 R | Missing |
NEA/CSNI-54 R | Missing |
NEA/CSNI-53 R | Missing |
NEA/CSNI-52 R | Missing |
NEA/CSNI-51 R | Missing |
NEA/CSNI-50 R | Missing |
NEA/CSNI-49 | Two-phase critical flow models: a technical addendum to the CSNI State of the Art Report (SOAR) on critical flow modelling, 1980. |
NEA/CSNI-48 | Analysis of the PISC trials results for alternative procedures: report no 6. - Ispra, Italy: CEC, 1980. Also referenced as: EUR 6371 EN |
NEA/CSNI-47 | First CSNI numerical benchmark problem: comparison report, 1980. |
NEA/CSNI-46 | Proceedings of the specialist meeting on reliability of the ultrasonic inspection of austenitic materials (1980 : Brussels, Belgium), 1980. |
NEA/CSNI-45 | Proceedings of the CSNI specialists meeting on nuclear aerosols in reactor safety (1980 : Gatlinburg, Tenn.), 1980. Also referenced as: NUREG/CR-1724. ORNL/NUREG/TM-404 |
NEA/CSNI-44/vol3 | Proceedings specialist meeting on probabilistic methods in seismic assessment for nuclear power plants, 1980. Vol 3. |
NEA/CSNI-44/vol2 | Proceedings specialist meeting on probabilistic methods in seismic assessment for nuclear power plants, 1980. Vol 2. |
NEA/CSNI-44/vol1 | Proceedings specialist meeting on probabilistic methods in seismic assessment for nuclear power plants, 1980. |
NEA/CSNI-43/Vol3 | Proceedings specialist meeting on regulatory review in the licensing process (7-9 November 1979, Madrid, Spain), 1980. Volume 3 |
NEA/CSNI-43/Vol2 | Proceedings specialist meeting on regulatory review in the licensing process (7-9 November 1979, Madrid, Spain), 1980. Volume 2 |
NEA/CSNI-43/Vol1 | Proceedings specialist meeting on regulatory review in the licensing process (7-9 November 1979, Madrid, Spain), 1980. Volume 1 |
NEA/CSNI-42 R | Missing |
NEA/CSNI-41 | Comparison report on OECD-CSNI Containment Standard Problem N° 1:'Steamline rupture within a chain of compartments', 1980. |
NEA/CSNI-40 | Status of LMFBR safety technology: fission gas release from fuel pins, 1980. |
NEA/CSNI-39 | CSNI Specialists meeting on plastic tearing instability (1979 : St.Louis, Mo.), 1980. Also referenced as: NUREG/CP-0010 |
NEA/CSNI-55 | Comparison report on OECD-CSNI LOCA standard problem N? 7: analysis of a reflooding experiment, 1979. |
NEA/CSNI-38 R | Missing |
NEA/CSNI-37/vol3 | Fourth CSNI Specialist meeting on fuel-coolant interaction in nuclear reactor safety (1979: Bournemouth, England), 1979. Vol. 3 |
NEA/CSNI-37/vol2 | Fourth CSNI Specialist meeting on fuel-coolant interaction in nuclear reactor safety (1979: Bournemouth, England), 1979. Vol. 2 Continue. |
NEA/CSNI-37/vol1 | Fourth CSNI Specialist meeting on fuel-coolant interaction in nuclear reactor safety (1979 : Bournemouth, England), 1979. Vol. 1 |
NEA/CSNI-35 | Safety and siting of nuclear installations near international borders in NEA member, 1979. |
NEA/CSNI-29 | Code assessment and applications program : United States standard problem 7 and international standard problem 5: final report, 1979. |
NEA/CSNI-51 | Meeting of a task force on problems of rare events in the reliability analysis of nuclear power plants (3rd : 1978 : Garching, Germany), 1978. |
NEA/CSNI-36 | Regulatory inspection of nuclear power plants in NEA Member countries, 1978. |
NEA/CSNI-34 R | Missing |
NEA/CSNI-33 | Proceedings of the specialists' meeting on the safety problems associated with the handling and storage of UF6 (1978 : Boekelo, The Netherlands), 1978. |
NEA/CSNI-32/vol2 | Proceedings of the specialists meeting on elastoplastic fracture mechanics (1978 : Daresbury, England), 1978. Vol. 2 |
NEA/CSNI-32/vol1 | Proceedings of the specialists meeting on elastoplastic fracture mechanics (1978 : Daresbury, England), 1978 . Vol. 1 |
NEA/CSNI-31 | Transient two-phase flow : proceedings of the 2nd CSNI specialists meeting, June 12-14, 1978. |
NEA/CSNI-30 | Comparison report on OECD-CSNI standard problem N?6: determination of water level and phase separation effects during the initial blowdown, 1978. |
NEA/CSNI-29 R | Missing |
NEA/CSNI-28/vol3 | Proceedings of specialist meeting on the 1976 Friuli earthquake and the antiseismic design of nuclear installations (1977 : Rome, Italy), 1978. Vol 3. |
NEA/CSNI-28/vol2 | Proceedings of specialist meeting on the 1976 Friuli earthquake and the antiseismic design of nuclear installations (1977 : Rome, Italy), 1978. Vol 2 |
NEA/CSNI-28/vol1 | Proceedings of specialist meeting on the 1976 Friuli earthquake and the antiseismic design of nuclear installations (1977 : Rome, Italy), 1978. |
NEA/CSNI-26 | Group of experts on reference seismic ground motions in nuclear safety assessments: report to CSNI, 1978. |
NEA/CSNI-25 | The Safety of the nuclear fuel cycle: preliminary report by a Working Group, 1978. |
NEA/CSNI-15 | CSNI Standard problem 3: comparison of LOCA analysis codes - Paris: OECD-NEA, 1978. |
NEA/CSNI-27 | Proceedings of the specialists' meeting on regulatory inspection practices in nuclear power plants - Madrid: Junta de Energia Nuclear, 1977. |
NEA/CSNI-27/cont | Proceedings of the specialists' meeting on regulatory inspection practices in nuclear power plants - Madrid: Junta de Energia Nuclear, 1977. Continued. |
NEA/CSNI-24 | Licensing systems and inspection of nuclear installations in NEA member countries: part II: flowcharts of licensing procedures= regime d'autorisation et d'inspection des installations nucleaires dans les pays de l'AEN, 1977. |
NEA/CSNI-23 | Proceedings: meeting of a task force on problems of rare events in the reliability analysis of nuclear power plants (1977 : Saclay, France), 1977. |
NEA/CSNI-22 | Reactor noise : SMORN II : proceedings of the Second Specialists Meeting on Reactor Noise, (Gatlinburg, Tennessee, USA, 19-23 September 1977), 1977. |
NEA/CSNI-21 R | Missing |
NEA/CSNI-20 R | Missing |
NEA/CSNI-19 | Scientific secretary's record of the meeting of the CSNI group of experts on the science of fuel-coolant interactions and of vapour explosions (1st : 1977 : Paris, France), 1977. |
NEA/CSNI-18 R | Missing |
NEA/CSNI-17 | CSNI LOCA standard problems - Paris, OECD-NEA, 1977. |
NEA/CSNI-15/-1 | Solution of CSNI standard problem 3 using computer code Firebird, 1977. |
NEA/CSNI-13 | Proceedings of specialist meeting on the behaviour of water reactor fuel elements under accident conditions (1976 : Spatind, Norway), 1977. Part II available online only. To request access to Part I, please contact the NEA Secretariat. |
NEA/CSNI-16 | Comparisons of the standard problem calculations with measured experimental data for semiscale test S-02-6, 1976. |
NEA/CSNI-14 | Proceedings of the specialists meeting on the ultrasonic inspection of reactor components (1976 : Daresbury, England), 1976. |
NEA/CSNI-12 R | Missing |
NEA/CSNI-11 | Transient two-phase flow : proceedings of the CSNI specialists meeting, August 3-4 1976, Toronto, 1976. |
NEA/CSNI-10 | Meeting of a task force on problems of rare events in the reliability analysis of nuclear power plants: proceedings, 1976. |
NEA/CSNI-9 | Physical and toxic properties of hazardous chemicals regularly stored and transported in the vicinity of nuclear installations, 1976. |
NEA/CSNI-8/vol2 | Proceedings of the third specialist meeting on sodium/fuel interaction in fast reactors, 1976. Vol. 2 also referenced as: PNC N251 76-12 |
NEA/CSNI-8/vol1 | Proceedings of the third specialist meeting on sodium/fuel interaction in fast reactors, 1976. Vol. 1 Also referenced as: PNC N251 76-12 |
NEA/CSNI-7 | Proceedings of the specialist meeting on the anti-seismic design of nuclear installations = compte-rendu de la reunion de specialistes sur la conception antisismique des installations nucleaires (1975 : Paris, France), 1976. |
NEA/CSNI-6/vol2 | OECD-NEA-CSNI specialist meeting: high temperature gas cooled reactor safety: current status (1975 : Petten, The Netherlands), 1976 . Vol. 2 |
NEA/CSNI-6/vol1 | OECD-NEA-CSNI specialist meeting: high temperature gas cooled reactor safety: current status (1975 : Petten, The Netherlands), 1976. Vol. 1 |
NEA/CSNI-5 | Proceedings of the joint NEACRP/CSNI specialists' meeting on new developments in three-dimensional neutron kinetics and review of kinetics benchmark calculations, 1975. Also referenced as: NEACRP-A-367. MRR 145 |
NEA/CSNI-4 | Newsletter of the NEA Computer Programme Library=Bulletin de la Bibliotheque AEN de Programmes de Calcul, 1975. Also referenced as: Newsletter of the NEA CPL.;19 |
NEA/CSNI-3 | Specialist meeting on the development and application of reliability techniques to nuclear plant (1974 : Liverpool), 1975. Also referenced as: SRD R41 |
NEA/CSNI-2 | Specialist meeting on sodium/fuel interaction in fast reactors (2nd : 1973 : Ispra, Italy), 1973. Also referenced as: EUR 5309 e |
NEA/CSNI-1 | C.S.I.N. Reunion de specialistes sur la securite des elements combustibles des reacteurs a eau (1973 : Saclay, France), 1973. |