The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...
Published date:
21 November 2023
28 -
30 November 2023
McMaster University, Hamilton, ON (Canada)
The Materials Modelling and Simulation for Nuclear Fuels (MMSNF) Workshop is a forum for the discussion of state-of-the-art modelling and simulation techniques for nuclear fuels and cladding material...
Published date:
20 November 2023
The task force developed best practice guidelines by performing a benchmark study on thermo-hydraulic modelling of heavy liquid metal coolant, e.g. lead and lead-bismuth eutectic (LBE) alloy.
Published date:
28 February 2020
The expert group monitored the feedback from version 0 of the Lead-bismuth eutectic (LBE) handbook, collected, analysed and checked the consistency of expected new results from ongoing heavy liquid m...
Published date:
28 February 2020
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
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
The CRISSUE-S Project was created to re-evaluate fundamental technical issues with the technology of light water reactors (LWRs).
Published date:
2 November 2023
17 -
18 October 2023
Seoul, Korea
Published date:
27 September 2023
Experts from 16 countries met on 13-15 September for the 24th annual Working Group on Fuel Safety GFS meeting in Paris.
Published date:
27 October 2023
The International Reactor Physics Experiment Evaluation (IRPhE) Technical Review Group provides the nuclear community with qualified benchmark data sets by collecting reactor physics experimental dat...
Published date:
10 November 2022
Image: QUENCH facility at KIT. Court. KIT.
The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...
Published date:
17 May 2023
1 -
6 October 2023
Sendai International Center, Miyagi, Japan
The 12th International Conference on Nuclear Criticality Safety (ICNC) was held in Sendai, Japan, on 1-6 October 2023. Twenty years after the last conference in Japan, which was held in Tokai-mura as...
Published date:
13 December 2022
The EGMUP Task Force on artificial intelligence and machine learning will design benchmark specifications to evaluate the performance of AI/ML in multi-physics modeling and simulation of reactor syst...
Published date:
4 October 2023
The Global Forum on Nuclear Education, Science, Technology and Policy acts as an inclusive network of experts in the nuclear energy sector, primarily from academia, focused on enabling the generation...
Published date:
2 October 2023
NEA/NSC/R(2023)8
The Task Force on Dose Rate Calculations for Irradiated Fuel Assembly was launched in 2015 to assess code predictions of dose rates from bare spent fuel assemblies and to benchmark multiple codes and...
Published date:
19 September 2023
NEA/NSC/R(2022)6
The goal of the Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) Subgroup on Experimental Needs for Criticality Safety Purposes (SG-5) was to highlight the needs of int...
Published date:
15 September 2023
The NEA launched the Nuclear Education, Skills and Technology (NEST) Framework in partnership with its member countries to help address important gaps in nuclear skills capacity building, knowledge t...
Published date:
13 September 2023
Burn-up credit is a safety approach that accounts for the reduction in the reactivity of configurations with spent nuclear fuel due to the change in their composition after irradiation.
Published date:
11 September 2023
6 September 2023 -
27 October 2023
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
Published date:
5 September 2023
NEA/NSC/R(2022)3/CORR
Please note that this report was initially published in November 2022 (NEA/NSC/R(2022)3) under erroneous benchmark number IIB; in this updated version (NEA/NSC/R(2022)3/CORR) this has been corrected ...
Published date:
30 November 2022
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
Published date:
2 August 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
The NEA Working Party on Nuclear Criticality Safety (WPNCS) held its bi-annual meetings in June 2023
Published date:
24 July 2023
Co-organised with the UK Atomic Energy Authority, the course took place on 20-22 June 2023.
Published date:
24 July 2023
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
28 -
31 May 2024
INFN Laboratori Nazionali di Frascati, Frascati, Italy
Published date:
18 July 2023
TCOFF-2 members discuss future activities.
Published date:
10 July 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
Published date:
29 September 2020
The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.
Published date:
13 June 2023
10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.
Published date:
19 June 2023
Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.
Published date:
16 June 2023
The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.
Published date:
14 June 2023
WPFM held meetings on 23-25 May 2023.
Published date:
13 June 2023
The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues.
Published date:
13 June 2023
Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...
Published date:
9 June 2023
Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM) addresses materials science aspects of nuclea...
Published date:
1 June 2023
Sustained performance of nuclear technology depends on access to a talented and well-qualified workforce, thus it is important to ensure that adequate infrastructures exist for education and training...
Published date:
22 July 2020
22 -
26 May 2023
Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy + virtual option on ZOOM
Published date:
17 May 2023
NEA/NSC/R(2022)5
This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...
Published date:
3 April 2023
NEA/NSC/R(2021)3
Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...
Published date:
17 February 2023
NEA/NSC/R(2021)5
Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...
Published date:
18 April 2023
5 -
6 June 2023
Oregon State University, Corvallis, Oregon, United States
Published date:
20 April 2023
The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
Published date:
24 April 2023
Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.
Published date:
21 April 2023
The WPRS met from 20-24 February 2023.
Published date:
17 March 2023
Expert groups on structural and fuel materials meet to advance materials science activities
Published date:
24 February 2023
Thermodynamic databases and accident prevention
Published date:
24 February 2023
International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.
Published date:
24 February 2023