Index to NEA/CSNI Documents

Please note that many reports are out of stock and cannot be requested.
Some reports Marked "R" are either in preparation or are restricted to members of the Committee on the Safety of Nuclear Installations (CSNI).

Search CSNI and CNRA documents

Reference

Title

NEA/CSNI/R(2014)13
Extension of CFD Codes Application to Two-Phase Flow Safety Problems - Phase 3
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
R
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
R
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
OECD-NEA WGFCS Workshop Safety of Long Term Interim Storage Facilities
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/VOL1
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
IPS-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)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
R
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<br>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<br>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<br>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<br>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<br>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<br>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. Available at www.oecd-nea.org/html/nsd/reports/2007/nea6298-benchmarking.html<br>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. - Available at www.nea.fr\html\nsd\reports\2007\nea6053-uncertainties.html<br>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.<br>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
ISP-45 (QUENCH 06 Test) - Final Comparison and Interpretation Report
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
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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 - Operator Training and Instrumentation Capabilities, 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
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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
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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 Eletronics - 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.<br>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<br>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.<br>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 <br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>also referenced as: OCDE/GD(96)196
NEA/CSNI/R(1996)22
Relevant thermal hydraulic aspects of advanced reactors design: status report, 1996.<br>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.<br>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.<br>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.<br>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.<br>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.<br>also referenced as: OCDE/GD(97)12
NEA/CSNI/R(1996)16
Evaluation of the separate effects tests (set) validation matrix, 1997.<br>also referenced as: OCDE/GD(97)9
NEA/CSNI/R(1996)15
Computer and compiler effects on code results: status report, 1997.<br>also referenced as: OCDE/GD(97)6
NEA/CSNI/R(1996)14
Degraded core quench: a status report, 1996.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>See also <a href="/documents/1999/sin/csni-r99-3.pdf">NEA/CSNI/R(99)3</a> <br>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.<br>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.<br>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.<br>also referenced as: OCDE/GD(96)197
NEA/CSNI/R(1995)21
In-vessel core degradation code validation matrix, 1996.<br>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.<br>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.<br>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<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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. <br>See also <a href="/documents/1996/sin/csni-r1996-01.pdf">NEA/CSNI/R(96)1</a> <br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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<br>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).<br>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.<br>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.<br>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.<br>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)<br>also referenced as: CSNI-131 (1987)
NEA/CSNI-121
Evaluation of the PISC-II trials results. - Final issue, 1986.<br>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.<br>also referenced as: S.P./I.07.C1.86.61
NEA/CSNI-119
Destructive examination of the PISC-II RRT plates. - Final issue, 1986.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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<br>also referenced as: S.P./I.07.C1.86.53
NEA/CSNI-117
A Summary of the PISC-II project. - Final issue, 1986.<br>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.<br>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.<br>also referenced as: KfK 3800
NEA/CSNI-94
The ultrasonic inspection of austenitic materials : State of the Art Report (SOAR), 1985.<br>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.<br>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
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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.<br>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.<br>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
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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.<br>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<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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.<br>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
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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.<br>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
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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
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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
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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<br>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.<br>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.<br>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.<br>also referenced as: SRD R41
NEA/CSNI-2
Specialist meeting on sodium/fuel interaction in fast reactors (2nd : 1973 : Ispra, Italy), 1973.<br>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.