The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countrie...
Published date:
28 August 2023
Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) meeting, 8 June 2021.
Published date:
30 June 2021
The United States and the Russian Federation have each agreed to dispose of 34 tonnes of weapons-grade plutonium that are beyond their defence needs. One effective way to dispose of this plutonium is...
Published date:
20 January 2006
Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...
Published date:
5 October 2010
In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...
Published date:
16 November 2007
In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...
Published date:
30 June 2006
In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...
Published date:
31 December 2003
The overall objective of the VVER-1000 Coolant Transient (V1000CT) Benchmark was to assess computer codes used in the safety analysis of water-water energetic reactor (VVER) power plants, specificall...
Published date:
2 August 2022
Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...
Published date:
22 August 2006
It is essential to calculate the structural integrity of reactor components with a high degree of accuracy in order to make correct decisions regarding plant lifetime at the design stage, safety marg...
Published date:
11 April 2006
NEA/NSC/DOC(1996)25
In this benchmark exercise the goal is to test the current state-of-the-art two-dimensional methods of calculating neutron flux to reactor components against the measured data of the VENUS-1 critical...
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1 January 1996
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3 April 2008
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1 January 1999
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25 October 2001
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22 May 2003
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26 October 2005
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Used or spent fuel criticality is associated with the scientific issues around as...
Published date:
24 March 2020
28 -
29 April 2006
Pisa, Italy
Published date:
18 December 2020
TVA Watts Bar Unit 1 Multi-Physics Benchmark
Published date:
19 July 2022
NEA/NSC/R(2022)4
Under the auspices of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) was established to co-ordinate scientific activities related to ad...
Published date:
29 November 2022
Future fuel cycle characteristics, feasibility and acceptability will be crucial for the continued development of nuclear energy, especially in the post-Fukushima context. Fuel cycle choices have bot...
Published date:
18 July 2013
The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.
Published date:
14 June 2023
Co-organised with the UK Atomic Energy Authority, the course took place on 20-22 June 2023.
Published date:
24 July 2023
The NEA Data Bank organised a PENELOPE training course at the University of Barcelona in Spain on 11-15 July 2022
Published date:
1 August 2022
U-Zr-O system miscibility gap in the liquid state. Source: Guéneau et al. Journal of Nuclear Materials 254 (1998), 158-174.
Published date:
5 May 2020
Third International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-3) – Programme
Published date:
3 March 2020
7 -
10 October 2013
Idaho National Laboratory, Idaho Falls, United States
The OECD Nuclear Energy Agency (NEA) organised the Third International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-3). The workshop was held in Idaho Falls, USA on 7-10 Oct...
Published date:
3 March 2020
Third Information Exchange Meeting on the Nuclear Production of Hydrogen including Second HTTR Workshop, Japan Atomic Energy Agency (JAEA), Oarai, Japan, 5 - 7 October 2005 - Programme
Published date:
24 November 2020
5 -
7 October 2005
Japan Atomic Energy Agency, Oarai, Japan
The NEA Nuclear Science Committee (NSC) had organised two previous information exchange meetings on the nuclear production of hydrogen. The last of these meetings was held in October 2003, where deve...
Published date:
5 October 2005
The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:
- oxide-carbide fuel (U-Pu-O-C, released Decemb...
Published date:
23 February 2023
Published date:
2 August 2023
Preparatory meeting for Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)...
Published date:
27 May 2021
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
TCOFF Phases
First Phase (2017-2020)
The Thermodynamic Characterisation of Fuel Debris and Fission Products ...
Published date:
6 October 2023
Published date:
1 January 1998
Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...
Published date:
10 December 2020
High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...
Published date:
19 July 2023
Performance assessment of repository concepts for the geological disposal of long-lived radioactive waste relies on the availability of thermodynamic data for many radionuclides and other elements un...
Published date:
29 August 2002
The OECD Nuclear Energy Agency (NEA) Strategic Plan serves as a guiding instrument that reflects the priorities of its member countries as the Agency addresses evolving needs in the exploration and a...
Published date:
25 January 2022
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:
19 July 2004
The Nuclear Energy Agency's High Priority Nuclear Data Request List (HPRL) is a compilation of the highest priority nuclear data requirements.
Published date:
4 December 2019
Published date:
10 November 2016
NEA/NSC/R(2022)1
There is significant international interest in the effects of temperature on criticality safety evaluations. Improved access to nuclear data, notably thermal scattering data S(α,β) for hydrogen in ic...
Published date:
2 November 2023
22 -
23 June 2023
IRSN, Fontenay-aux-Roses, France
In the early decades of nuclear reactor development, many countries built and operated zero-power facilities in which many different critical arrangements of materials were studied. These flexible ex...
Published date:
6 June 2023
The NEA workshop gathered experts to discuss the challenges and opportunities related to the demise of zero power reactors.
Published date:
4 July 2023
Published date:
23 March 2020
The fourth international NEA workshop on Technology and Components of Accelerator‑Driven Systems (TCADS‑4), 14‑17 October 2019.
Published date:
18 November 2019
Published date:
28 June 2011
The Technical Review Group (TRG) for the International Assay Data of Spent Nuclear Fuel Database (SFCOMPO) lies under the direction of the Working Party on Nuclear Criticality Safety (WPNCS).
Published date:
13 April 2021
6 September 2023 -
27 October 2023
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
Published date:
5 September 2023