NEA/CSNI/R(2016)6/VOL1
Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenari...
Published date:
19 April 2016
NEA/CSNI/R(2016)5
The workshop objectives relative to reviewing and discussing the state-of-the-art knowledge of iodine and ruthenium behaviour in NPP accidents gained through research projects and progress made in th...
Published date:
30 May 2016
NEA/CSNI/R(2016)4
Single-phase computational fluid dynamics (CFD) is used more and more for design and safety issues related to light-water reactor (LWR) thermal hydraulics. Over the past ten years, the Working Group ...
Published date:
1 February 2016
NEA/CSNI/R(2016)3
Criticality safety is an integral component of ensuring the continued safe operation of current reactor and fuel cycle facilities, as well as addressing new and interesting challenges that are expect...
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31 August 2016
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21 September 2005
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20 September 2005
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12 October 2007
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15 November 2007
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3 October 2008
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14 December 1989
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 ...
Published date:
23 February 2016
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...
Published date:
1 January 2016
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...
Published date:
6 May 2019
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...
Published date:
6 February 2019
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...
Published date:
11 June 2018
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 (...
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2 July 2018
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...
Published date:
1 March 2018
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...
Published date:
11 January 2018
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...
Published date:
16 April 2018
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 ...
Published date:
1 January 2018
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 ...
Published date:
8 January 2018
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...
Published date:
1 November 2017
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...
Published date:
31 January 2018
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...
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11 April 2018
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...
Published date:
24 August 2017
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...
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23 May 2017
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...
Published date:
17 January 2018
NEA/CSNI/R(2017)4
Management of spent fuel (SF) and high-level waste (HLW) is fundamental to the fuel cycle safety. The original management strategies were established on the basis of limited interim storage periods o...
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19 January 2017
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22 May 2017
NEA/CSNI/R(2017)2/ADD1
International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain.
In this work, a complete algorithm for monitoring fatigue was developed for nuclear...
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17 July 2017
NEA/CSNI/R(2017)2
This is a summary report from the International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain. Over 90 specialists from 21 countries attended th...
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17 July 2017
NEA/CSNI/R(2018)3
The Metallic Component Margins under High Seismic Loads (MECOS) Project is an international programme organised under an initiative of the NEA. The main objective of the MECOS Project is to quantify ...
Published date:
12 November 2018
NEA/CSNI/R(2018)5
This report documents a study performed on a set of common-cause failure (CCF) events of Emergency Diesel Generators (EDG) at nuclear power plants. In May 2000, the ICDE Project published a report su...
Published date:
26 September 2018
NEA/CSNI/R(2018)6
The Source Term Evaluation and Mitigation Project (STEM) project, hosted by the Nuclear Energy Agency (NEA) and operated by the Institut de Radioprotection et de Sûreté Nucléaire (French Institute of...
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17 March 2020
NEA/CSNI/R(2018)7
It has long been recognised that external hazards can present a potential common cause source of initiating events that could challenge nuclear power plant safety. Modelling of these hazards is a com...
Published date:
2 April 2019
Feedback on operating experience from nuclear power plants is intended to help avoid occurrence or recurrence of safety-significant events. Well-established feedback systems exist on the national and...
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31 December 2004
This technical opinion paper provides the reader with a concise description of both the benefits and disadvantages of using probabilistic safety assessment (PSA) to analyse operational events in nucl...
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2 December 2004
Probabilistic safety analyses (PSAs) for many of the nuclear power plants throughout the world are being maintained as "living PSAs" (LPSAs), being updated to take account of changes to the design an...
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1 February 2005
This technical opinion paper represents the consensus of risk analysts in NEA member countries on the current state of the art of human reliability analysis (HRA) in probabilistic safety assessment (...
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9 February 2004
Nuclear licensees are increasingly required to adapt to a more challenging commercial environment as electricity markets are liberalised. One of the costs that is often perceived as being amenable to...
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9 June 2004
This technical opinion paper represents the consensus of risk analysts in NEA member countries on the current state of the art of level-2 probabilistic safety assessment (PSA) and its applications in...
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20 April 2007
Errors during maintenance and periodic testing are significant contributors to plant events. These errors may not always be revealed by post-maintenance tests and may remain undetected for extended p...
Published date:
26 February 2009
Nuclear power plant modifications may be needed for a number of different reasons. These include physical ageing of plant systems, structures and components; obsolescence in hardware and software; fe...
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3 February 2009
It is a dynamic time for the nuclear power sector. Existing reactor control rooms are undergoing various forms of modernisation. New reactors are being built in many countries and advanced reactors a...
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11 December 2009
The way in which nuclear licensees’ organisations are structured and resourced clearly has a potential impact on nuclear safety. As experience has continually demonstrated, operating organisations wi...
Published date:
15 May 2012
Managing the ageing of fuel cycle facilities (FCFs) means, as for other nuclear installations, ensuring the availability of required safety functions throughout their service life while taking into a...
Published date:
31 December 2013
