NEA/CSNI(1987)132
Published date:
1 January 1987
The Co-ordinated Research and Environmental Surveillance Programme relevant to sea disposal of radioactive waste (CRESP) was created in 1981 in the framework of the 1977 Decision of the OECD Council ...
Published date:
1 January 1996
NEA/CSNI/R(1998)13
Published date:
1 January 1998
NEA/CSNI/R(1999)2
Published date:
16 February 1999
NEA/CSNI/R(2000)20
Published date:
23 August 2000
Published date:
5 February 2001
NEA/CSNI/R(2001)4
A Report by the OECD Support Group on the VVER Thermal-Hydraulic Code Validation Matrix (2001)
Published date:
16 February 2001
NEA/CSNI/R(2001)8
Published date:
10 April 2001
NEA/CSNI/R(2001)10
Published date:
26 April 2001
NEA/CSNI/R(2002)19
Published date:
15 July 2002
NEA/CSNI/R(2003)12
Activity report of the OECD NEA Bubbler Condenser Steering Group, January 2003
Published date:
31 March 2003
NEA/CSNI/R(2003)15
Published date:
11 July 2003
NEA/CSNI/R(2003)19
Published date:
28 November 2003
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...
Published date:
30 January 2004
NEA/CSNI/R(2004)23
The focus of the Material Scaling (MASCA) Project was to investigate in detail the chemical behaviour of corium in contact with structural materials, with emphasis mainly on steel. This report provid...
Published date:
1 November 2004
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 ...
Published date:
1 June 2007
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...
Published date:
25 January 2008
NEA/CSNI/R(2008)8
Published date:
16 June 2008
NEA/CSNI(1990)181
Published date:
7 May 2010
This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for sodium fast reactors and identifies priorities for organising international co-op...
Published date:
15 April 2011
NEA/CSNI/R(2011)12
In this document, the general coding guidelines for the OECD NEA ICDE Project (International Common Cause Failure Data Exchange) are presented with explanations and appendices for each analysed compo...
Published date:
21 February 2012
NEA/CSNI/R(2013)2
Published date:
7 February 2013
NEA/CSNI/R(2013)4
Published date:
18 March 2013
NEA/CSNI/R(2015)11
This report documents a study performed on a set of ICDE events related to heat exchangers. The events studied here had been collected in the ICDE database. Organisations from Canada, Germany, Japan,...
Published date:
1 April 2013
NEA/CSNI/R(2015)17
In the light of the TEPCO Fukushima accident, this report documents a study performed on a set of common-cause failure (CCF) events due to external factors, meaning that not only storms and hurricane...
Published date:
20 October 2015
The OECD Nuclear Energy Agency (NEA) has just published a new report entitled Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt.
Published date:
29 February 2016
The OECD Nuclear Energy Agency (NEA) has just published a new report entitled Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt.
Published date:
29 February 2016
This Strategic Plan is intended to guide the NEA as it seeks to meet the evolving needs of member countries in the application and exploration of nuclear science and technology. The plan includes an ...
Published date:
22 December 2016
Published date:
13 June 2017
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
The brochure provides background information about the NEA.
Published date:
10 September 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(2019)3
The ICDE project allows multiple countries to collaborate and exchange CCF data to enhance the quality of risk analyses, which include CCF modelling. Because CCF events are typically rare, most count...
Published date:
21 January 2019
Risk assessments are used to determine the probability of harmful events at a nuclear plant. They are valuable for determining the relative benefit and better selection of safety enhancements.
Published date:
17 March 2020
Accident analysis and management focusses on understanding the causes and consequences of an accident at a nuclear facility, and on how to manage an accident through prevention and mitigation.
Published date:
17 March 2020
Nuclear facilities rely on a robust electrical system to power primary and back-up systems required to safely respond to a wide variety of challenging events.
Published date:
17 March 2020
Demonstrating the safety of a nuclear facility requires that the consequences of all possible threats be considered, including external hazards such as severe weather, floods and earthquakes.
Published date:
18 March 2020
The fuel for a nuclear reactor is both the source of the fission energy that is used to produce electricity and the source of radioactive material during an accident.
Published date:
18 March 2020
The facilities associated with nuclear fuel from mining to fabrication to post-irradiation management have some specific safety concerns that are different from those of nuclear reactors.
Published date:
18 March 2020
Reactor components and structures degrade by exposure to heat, environmental conditions and radiation. It is vital to understand ageing processes to ensure that safety criteria continue to be met.
Published date:
18 March 2020
The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment building following a severe accident. This...
Published date:
2 April 2020
The Cabri International Project (CIP) began in March 2000 to study the behaviour of fuel rods, specifically cladding, during a reactivity-initiated accident (RIA) in a pressurised-water reactor (PWR)...
Published date:
2 April 2020
The main purpose of the project is to encourage multilateral co-operation in the collection and analysis of data relating to fire events. The objectives of the NEA Fire Project are to:
Published date:
3 April 2020
The acronym PRISME comes from the French phrase propagation d’un incendie pour des scénarios multi-locaux élémentaires, which in English can be translated as "fire propagation in elementary, multi-ro...
Published date:
3 April 2020
The Halden Reactor Project has been in operation since 1958 and is the oldest NEA joint project. It brings together an important international technical network in the area of nuclear safety ranging ...
Published date:
6 April 2020
The HEAF Project was planned as a three-year programme to be conducted by the United States Nuclear Regulatory Commission (NRC) at a facility in the US. The project's aim was to conduct experiments i...
Published date:
6 April 2020
HYMERES phases
First phase (2013-2016)
The main objective of the first phase of the Hydro...
Published date:
6 April 2020
Common-cause failure (CCF) events can significantly affect the availability of nuclear power plant safety systems. In recognition of this, CCF data is systematically collected and analysed in several...
Published date:
7 April 2020
The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facilities (TAREF) was established in 2007 and issued a report on the experimental facilities f...
Published date:
7 April 2020
The goal of the Rod Bundle Heat transfer (RBHT) Project is to conduct experiments in the RBHT facility in the United States in order to:
- simulate reflood scenarios in a prototypical PWR rod bundle s...
Published date:
8 April 2020
English