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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
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
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
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
Main Results of the MASCA1 and 2 Projects: Integrated Report
NEA/CSNI/R(2007)15

The Material Scaling (MASCA) Project investigated in-vessel phenomena during a severe accident. In particular, it addressed the influence of the chemical composition of the molten corium on the heat ...

English Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures Safety research …
Published date: 1 June 2007
NEA Document
ICDE Project Report: Collection and Analysis of Common-Cause Failures of Switching Devices and Circuit Breakers
NEA/CSNI/R(2008)1

Common-cause-failure (CCF) events can significantly impact the availability of safety systems of nuclear power plants. For this reason, the International Common Cause Failure Data Exchange (ICDE) pro...

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: 25 January 2008
NEA Document
ICDE Project Report: Collection and Analysis of Common-cause Failures of Level Measurement Components
NEA/CSNI/R(2008)8
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: 16 June 2008
NEA Document
Summary Report on OECD/NEA Seismic Workshops
NEA/CSNI/R(2008)7

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has as a general mandate to advance the current understanding o...

English WGIAGE Nuclear safety research CSNI Safety of components and structures …
Published date: 17 July 2008
NEA Document
A Decade of CSNI Activities in the Area of Ageing of Nuclear Power Plant Concrete Structures
NEA/CSNI/R(2008)14

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has as a general mandate to advance the current understanding o...

English WGIAGE Nuclear safety research CSNI Safety of components and structures …
Published date: 17 December 2008
NEA Document
Ability of Current Advanced Codes to Predict Core Degradation, Melt Progression and Reflooding: Benchmark Exercise on an Alternative TMI-2 Accident Scenario
NEA/CSNI/R(2009)3

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

English WGAMA Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety assessment CSNI Safety Safety of components and structures Risk assessment Benchmark Probabilistic risk assessment …
Published date: 3 August 2009