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NEA Document
Recent Developments in Level 2 PSA and Severe Accident Management
NEA/CSNI/R(2007)16
English WGRISK CSNI
Published date: 15 November 2007
NEA Document
HRA Data and Recommended Actions to Support the Collection and Exchange of HRA Data: CSNI WGRisk Report
NEA/CSNI/R(2008)9
English WGRISK CSNI
Published date: 3 October 2008
NEA Document
Status of PSA programmes in member countries, 1989
NEA/CSNI(1989)172
English WGRISK CSNI
Published date: 14 December 1989
NEA Document
The Nuclear Energy Agency–Paul Scherrer Institut Computational Fluid Dynamics Benchmark Exercise
NEA/CSNI/R(2016)2
The OECD Nuclear Energy Agency-Paul Scherrer Institut (NEA-PSI) Benchmark was initiated to test the capability of state-of-the-art computational fluid dynamics (CFD) and dedicated containment codes ...
English CFD Nuclear safety research CSNI Benchmark …
Published date: 23 February 2016
NEA Document
Computational Fluid Dynamics for Nuclear Reactor Safety-5 (CFD4NRS-5): Workshop Proceedings
NEA/CSNI/R(2016)1
This present workshop was held in Zurich, Switzerland on 9-11 September 2014. It is the 5th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS-5), in the biennial series of...
English CFD WGAMA CSNI Proceedings …
Published date: 1 January 2016
NEA Document
Computational Fluid Dynamics for Nuclear Reactor Safety Applications-6 (CFD4NRS-6): Workshop Proceedings
NEA/CSNI/R(2017)20

The present report summarises the 6th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS-6) in the biennial series, supported by the Nuclear Energy Agency Worki...

English WGAMA Nuclear safety research CSNI Proceedings …
Published date: 6 May 2019
NEA Document
NEA Benchmark Exercise: Computational Fluid Dynamic Prediction and Uncertainty Quantification of a GEMIX Mixing Layer Test
NEA/CSNI/R(2017)19
The main objectives of the current activity are the promotion, test and evaluation of various methodologies for uncertainty quantification in computational fluid dynamics (UQCFD) for nuclear reactor...
English Uncertainty quantification Nuclear safety research CSNI
Published date: 6 February 2019
NEA Document
Phenomena Identification and Ranking Table: R&D Priorities for Loss-of-Cooling and Loss-of-Coolant Accidents in Spent Nuclear Fuel Pools
NEA/CSNI/R(2017)18
The main objective of the report is to identify research and development priorities related to loss-of-cooling and loss-of-coolant accidents in spent fuel pools. This is done by applying a PIRT proc...
English Spent fuel Nuclear safety research CSNI WGFS …
Published date: 11 June 2018
NEA Document
Informing Severe Accident Management Guidance and Actions for Nuclear Power Plants through Analytical Simulation
NEA/CSNI/R(2017)16

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

English WGAMA Accident analysis and management Nuclear safety research CSNI …
Published date: 2 July 2018
NEA Document
Status Report on Ex-Vessel Steam Explosion
NEA/CSNI/R(2017)15
The Status Report on Ex-Vessel Steam Explosion (EVSE) summarises the significant progress made in the field of Fuel Coolant Interaction/Steam Explosion (FCI/SE) knowledge during these last ten years...
English Nuclear safety research CSNI
Published date: 1 March 2018
NEA Document
Investigating Heat and Smoke Propagation Mechanisms in Multi-Compartment Fire Scenarios: Final Report of the PRISME Project
NEA/CSNI/R(2017)14
Fire hazards analyses (FHA) and probabilistic fire safety analyses (Fire PSA) have demonstrated that fire may be an important contributor to core damage frequency and other major plant damage states...
English Nuclear safety research CSNI
Published date: 11 January 2018
NEA Document
Understanding the Impact of External Hazards on Nuclear Facilities: Severe Weather and Storm Surge
NEA/CSNI/R(2017)13
The March 2011 accident at Fukushima Daiichi nuclear power plant triggered discussions about the natural external events that are low-frequency but high-consequence. In order to address these issues...
English WGEV Nuclear safety research CSNI Proceedings …
Published date: 16 April 2018
NEA Document
Developments in Fuel Cycle Facilities after the Fukushima Daiichi Nuclear Power Station Accident: Workshop Proceedings (Appendix 3)
NEA/CSNI/R(2017)12/ADD1

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

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

English Fuel cycle facility safety Nuclear safety research CSNI Proceedings …
Published date: 1 January 2018
NEA Document
Developments in Fuel Cycle Facilities after the Fukushima Daiichi Nuclear Power Station Accident: Workshop Proceedings
NEA/CSNI/R(2017)12
The main objective of the workshop, held in Aomori City, Japan on 15-17 November 2016, was to review and discuss national activities, plans and regulatory approaches by member countries in light of ...
English Fuel cycle facility safety Nuclear safety research CSNI Proceedings …
Published date: 8 January 2018
NEA Document
Benchmark Results on the Analytical Evaluation of the Fracture Mechanic Parameters K and J
NEA/CSNI/R(2017)11

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

English WGIAGE Nuclear safety research CSNI
Published date: 1 November 2017
NEA Document
Summary and Conclusions of the Joint PKL3-ATLAS Workshop on Analytical Activities
NEA/CSNI/R(2017)10

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

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

English Nuclear safety research CSNI Joint project
Published date: 31 January 2018
NEA Document
Summary Report of the NEA Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS) Joint Project
NEA/CSNI/R(2017)9

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

English Nuclear safety research CSNI Joint project
Published date: 11 April 2018
NEA Document
Workshop on the Collection and Analysis of Emergency Diesel Generator Common-Cause Failures Impacting Entire Exposed Populations: International Common-Cause Failure Data Exchange (ICDE) Project Report
NEA/CSNI/R(2017)8

This report documents a study performed on a set of common-cause failure (CCF) events for diesel generators. The events were derived from the International CCF Data Exchange (ICDE) database and the s...

English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Safety research Risk assessment …
Published date: 24 August 2017
NEA Document
Report on the Testing Phase (2014-2016) of the High Energy Arcing Fault Events (HEAF) Project: Experimental Results from the International Energy Arcing Fault Research Programme
NEA/CSNI/R(2017)7
This report documents an experimental programme designed to investigate the High Energy Arcing Fault (HEAF) phenomena. The most recent international nuclear power plant (NPP) operating experience wi...
English Nuclear safety research CSNI Joint project
Published date: 23 May 2017
NEA Document
Solving Thermal Hydraulic Safety Issues for Current and New Pressurised Water Reactor Design Concepts: Primary Coolant Loop Test Facility (PKL2) Project – Final Report
NEA/CSNI/R(2017)6

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

English Nuclear safety research CSNI Pressurised water reactors
Published date: 17 January 2018