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NEA Document
TMI-2 Examination Results from the OECD-CSNI Programme: Volume 2
NEA/CSNI/R(1992)9/VOL2
English Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety assessment CSNI Joint project Safety Safety of components and structures Risk Risk assessment Probabilistic risk assessment …
Published date: 17 August 2006
NEA Document
Progress Made in the Last Fifteen Years Through Analyses of the TMI-2 Accident Performed in Member Countries
NEA/CSNI/R(2005)1

The TMI-2 accident keeps providing unique full scale data giving opportunities to check the ability of the codes to model overall plant behaviour and to perform many sensitivity and uncertainty calcu...

English Three Mile Island WGAMA Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety assessment CSNI Safety Safety of components and structures Risk assessment Probabilistic risk assessment …
Published date: 10 March 2005
NEA Document
Third International Conference on Fatigue of Reactor Components
NEA/CSNI/R(2004)21

The Third International Conference on Fatigue of Reactor Components held in Seville, Spain on 3-6 October 2004 was co-organised by the EPRI, the US NRC and the OECD NEA Committee on the Safety of Nuc...

English WGIAGE Nuclear safety research CSNI Safety of components and structures Proceedings …
Published date: 5 January 2005
NEA Document
Experimental Facilities for Earthquake Engineering Simulation Worldwide: Are Large Testing Facilities for Nuclear Power Plants Design and Verification at Risk?
NEA/CSNI/R(2004)10

In the report “Nuclear Safety Research in OECD Countries: Summary Report of Major Facilities and Programmes at Risk“ published by the NEA/CSNI Senior Group of Experts on Nuclear Safety Research Facil...

English WGIAGE Nuclear safety research CSNI Safety of components and structures …
Published date: 7 July 2004
NEA Document
ICDE General Coding Guidelines: Technical Note
NEA/CSNI/R(2004)4

Several member countries of the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA) established the International Common-Cause Failure Data Exchange Project...

English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
Published date: 30 January 2004
NEA Document
ICDE Project Report: Collection and Analysis of Common-cause Failures of Batteries
NEA/CSNI/R(2003)19
English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
Published date: 28 November 2003
Publications and Reports
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume IV

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

English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
Published date: 19 November 2003
NEA Document
ICDE Project Report: Collection and Analysis of Common-cause Failure of Check Valves
NEA/CSNI/R(2003)15
English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
Published date: 11 July 2003
NEA Document
Lower Head Failure Project Final Project Report
NEA/CSNI/R(2002)27

Volume 1 – Integral Experiments and Material Characterization

English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures …
Published date: 28 May 2003
NEA Document
Answers to Remaining Questions on Bubbler Condenser
NEA/CSNI/R(2003)12

Activity report of the OECD NEA Bubbler Condenser Steering Group, January 2003

English Risk assessment Fuel cycle facility safety Nuclear safety research CSNI Safety of components and structures Pressurised water reactors Risk Safety research …
Published date: 31 March 2003
Publications and Reports
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume III

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

English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
Published date: 22 November 2002
NEA Document
ICDE Project Report: Collection and Analysis of the Common-cause Failure of Safety and Relief Valves
NEA/CSNI/R(2002)19
English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
Published date: 15 July 2002
NEA Document
ICDE Project Report: Collection and Analysis of Common-cause Failures of Motor-operated Valves
NEA/CSNI/R(2001)10
English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
Published date: 26 April 2001
NEA Document
Proceedings of the ICDE Workshop on the Qualitative and Quantitative Use of ICDE Data, Stockholm, Sweden, 12-13 June 2001
NEA/CSNI/R(2001)8
English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Proceedings Safety research Risk assessment …
Published date: 10 April 2001
NEA Document
Validation Matrix for the Assessment of Thermal-Hydraulic Codes for VVER LOCA and Transients
NEA/CSNI/R(2001)4

A Report by the OECD Support Group on the VVER Thermal-Hydraulic Code Validation Matrix (2001)

English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures Codes and programs Safety research …
Published date: 16 February 2001
NEA Document
Bubbler Condenser-Related Research Work: Present Situation
NEA/CSNI/R(2001)3

September 2000

English Risk assessment Fuel cycle facility safety Nuclear safety research CSNI Safety of components and structures Pressurised water reactors Risk Safety research …
Published date: 5 February 2001
Publications and Reports
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume II

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

English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
Published date: 22 December 2000
NEA Document
RASPLAV Seminar 2000: Summary and Conclusions
NEA/CSNI/R(2000)23

14-15 November 2000, Munich, Germany

English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures …
Published date: 13 December 2000
NEA Document
ICDE Project Report: Collection and Analysis of Common-cause Failures of Emergency Diesel Generators
NEA/CSNI/R(2000)20
English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
Published date: 23 August 2000
NEA Document
ICDE Project Report: Collection and Analysis of Common-cause Failures of Centrifugal Pumps
NEA/CSNI/R(1999)2
English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Codes and standards in nuclear safety Safety research Risk assessment …
Published date: 16 February 1999