24 -
27 October 2023
NEA Headquarters, Boulogne-Billancourt, France
The NEA is organising the 16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT) on 24-27 October 2023. The meeting will be held at the NEA offices...
Published date:
23 October 2023
21 -
25 February 2022
ZOOM virtual meeting
Published date:
7 February 2022
Publié chaque année, le Rapport annuel de l’AEN présente un aperçu des activités et publications de l’AEN pour une année donnée, ainsi que les derniers développements du secteur de l’énergie nucléair...
Published date:
8 December 2023
Published every year, the NEA Annual report includes an overview of NEA's activities and publications produced during the year, as well as the latest developments in nuclear energy sector around the ...
Published date:
8 December 2023
20 -
24 February 2023
NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France) with a remote access option
Published date:
30 January 2023
19 -
23 February 2024
NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France), remote access only under exceptional circumstances
Published date:
29 November 2023
27 June 2022 -
1 July 2022
OECD headquarters, Paris XVI
Published date:
1 June 2022
The project participants, who come from 19 organisations in 8 countries, met in December 2023 in Karlsruhe.
Published date:
21 December 2023
NEA/NSC/R(2020)4
Advanced nuclear fuel cycles to improve the safety, sustainability and economics of nuclear energy are being investigated worldwide. Partitioning and transmutation (P&T) is one of the candidate techn...
Published date:
11 October 2022
The NEA and IAEA jointly organised an international workshop in Vienna, Austria, on 2-6 October 2023.
Published date:
21 November 2023
WPNCS bi-annual event brought together 80 experts from 17 member countries.
Published date:
7 February 2022
The 2023 MMSNF takes place in Canada.
Published date:
14 December 2023
WPFM held meetings on 23-25 May 2023.
Published date:
13 June 2023
The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) and its expert groups co-ordinate benchmark activities on Reactor Single- and Multi-Physics. The benchmark ac...
Published date:
21 December 2023
An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.
Published date:
2 August 2022
The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...
Published date:
25 April 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
Published date:
18 January 2024
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)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
Many of the failures that occur in nuclear fuel rods in light water reactors around the world are caused by the phenomenon of mechanical interaction between pellets and cladding (PCMI). The process i...
Published date:
30 April 2024
Many of the failures that occur in nuclear fuel rods in light water reactors around the world are caused by the phenomenon of mechanical interaction between pellets and cladding (PCMI). The process i...
Published date:
30 April 2024
30 October 2023
13:00-15:00 CET, Online
Recent performance breakthroughs in Artificial Intelligence (AI) and Machine Learning (ML) have led to unprecedented interest in AI/ML among nuclear engineers. However, the lack of dedicated benchmar...
Published date:
6 December 2023
The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.
Published date:
13 June 2023
The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...
Published date:
19 July 2022
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
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
This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).
Published date:
7 March 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
Published date:
17 January 2023
NEA/NSC/R(2019)6
The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...
Published date:
18 November 2021
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 Criticality Safety Benchmark Evaluation Project (ICSBEP) released the first version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experime...
Published date:
25 April 2022
Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...
Published date:
12 April 2023
To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...
Published date:
19 July 2022
The event gathered 129 participants from 75 international institutions.
Published date:
6 October 2022
WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.
Published date:
9 June 2022
The WPRS met from 20-24 February 2023.
Published date:
17 March 2023
View of Dragon Reactor. Photo: AEA Technology.
In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...
Published date:
14 October 2022
EGPRS Task Force members met on 3 April 2023.
Published date:
7 April 2023
NEA/NSC/R(2019)7
The modelling and simulation of nuclear systems allow scientists and engineers to probe aspects of the operation of these systems beyond what has been precisely measured. This has numerous applicatio...
Published date:
11 October 2022
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 expert group primarily acted as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance.
Published date:
18 October 2022
Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Fuel Materials (EGFM) focuses on materials science aspects of...
Published date:
3 March 2023
The expert group dealt with the activities associated with the certification of experimental data and benchmark models along with establishing the processes and procedures for using the data and benc...
Published date:
23 November 2021
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) performs specific tasks associa...
Published date:
6 December 2023
Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...
Published date:
6 December 2023
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...
Published date:
8 March 2023
The Expert Group on Reactor Systems Multi-Physics (EGMUP) advances the state of the art in establishing processes and procedures for certifying experimental data and benchmarking multi-physics multi-...
Published date:
6 December 2023
The Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF) dealt with the various aspects of the modelling and design of accelerator shield systems and radiatio...
Published date:
19 November 2021
Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Structural Materials (EGSM) focuses on materials science aspe...
Published date:
3 March 2023
The expert group provided advice to the Working Party on Scientific Issues of Reactor Systems (WPRS) on the scientific development needs (data and methods, validation experiments, scenario studies) o...
Published date:
27 October 2021
Expert groups on structural and fuel materials meet to advance materials science activities
Published date:
24 February 2023
The NEA Working Party on Nuclear Criticality Safety (WPNCS) held its bi-annual meetings in June 2023
Published date:
24 July 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
The benchmark will predict the Critical Heat Flux (CHF).
Published date:
22 November 2023
2 -
23 May 2023
Online training & in-person event on 22-23 May 2023 in Bologna, Italy
Published date:
11 December 2023
The first QUENCH-ATF joint project test was successfully completed by the KIT team on 17 July 2022.
Published date:
5 August 2022
Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark
Published date:
2 August 2022
Heavy liquid metals such as lead or lead-bismuth have been proposed and investigated as coolants for fast reactors since the 1950s. More recently, there has been renewed interest worldwide in the use...
Published date:
26 January 2024
The NEA Expert Group on Innovative Structural Materials (EGISM) organised a workshop on 19-21 October 2021 together with the Spanish Center for Energy, Environmental and Technological Research (CIEMA...
Published date:
3 November 2021
High-temperature gas-cooled reactors (HTGRs), also known as very-high-temperature reactors (VHTR) are Generation IV reactors that can operate at very high temperatures and use a graphite-moderated ga...
Published date:
22 June 2022
The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
Published date:
24 April 2023
NEA/NSC/R(2022)2
Under the guidance of the NEA Nuclear Science Committee (NSC), the Expert Group on Improvement of Integral Experiments Data for Minor Actinide Management (EGIEMAM-II) was established to recommend nec...
Published date:
4 March 2024
“Improving Cross-disciplinary and Transversal Skills for the Severe Accidents Community” approved by NEST Management Board.
Published date:
18 December 2023
Thermodynamic databases and accident prevention
Published date:
24 February 2023
TCOFF-2 members discuss future activities.
Published date:
10 July 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 primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allo...
Published date:
10 November 2022
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...
Published date:
10 November 2022
International Fuel Performance Experiments (IFPE) is a data collection of nuclear fuel performance experiments for the purpose of code development and validation.
Published date:
18 January 2024
The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.
Published date:
13 December 2022
The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at ...
Published date:
9 November 2022
The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the IRPhE Handbook DVD. This database and corresponding user interface allows easy access to handbook inform...
Published date:
17 March 2022
ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings, October 2021.
Published date:
25 October 2021
The International School on Simulation of Nuclear Reactor Systems (SINUS) provides hybrid, hands-on-training encompassing multiphysics modelling and simulation (M&S) and associated validation, verifi...
Published date:
21 December 2023
Published date:
6 December 2023
5 -
6 June 2023
Oregon State University, Corvallis, Oregon, United States
Published date:
20 April 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
NEA/NSC/R(2021)4
The understanding of nuclear physics and the associated uncertainties is essential to the modelling of all nuclear systems. Nuclear reaction probabilities, emitted particle energies and angles, fissi...
Published date:
8 February 2023
Collected sources of primary documentation for reactor physics benchmarks.
Published date:
14 April 2022
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
JANIS (Java-based nuclear information software) is an application designed to facilitate the visualisation and manipulation of nuclear data. JANIS will be helpful to engineers and physicists who use ...
Published date:
24 November 2022
The NEA Data Bank Nuclear Data Service (NDS) organised the Joint Evaluated Fission and Fusion (JEFF) Nuclear Data Week (NDW) on 25-29 April 2022.
Published date:
20 May 2022
This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-100...
Published date:
19 July 2022
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
The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests ...
Published date:
19 July 2022
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
Building on the NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group on U...
Published date:
19 July 2022
15 -
19 April 2024
Lawrence Livermore National Laboratory (LLNL), California, USA
Published date:
2 February 2024
The meeting marked an important transition for the framework with the launch of four new Joint Experimental Programmes (JEEPs).
Published date:
24 April 2024
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
FIDES-II member assembled at the Japan Atomic Energy Agency (JAEA) in Mito, Japan.
Published date:
23 November 2023
MeshTal Viewer user manual
Published date:
25 November 2022
Recent meetings of groups working under the aegis of the Framework for Irradiation Experiments (FIDES) have demonstrated that the international community is enthusiastic and on a strong course to ful...
Published date:
5 May 2022
Multi-physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) Benchmark
Published date:
19 July 2022
In November 2023, the NEA Data Bank held two beginner level courses in Paris, France.
Published date:
21 November 2023
Courses were held in November 2022 in paris, France.
Published date:
14 December 2022
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
17 -
18 October 2023
Seoul, Korea
Published date:
27 September 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
The meetings took place in April 2024 in the United States.
Published date:
25 April 2024
The 2021 edition can be downloaded online.
Published date:
22 November 2022
Nuclear Data Sensitivity Tool (NDaST), aims to provide rapid feedback on the effect of changes to nuclear data on integral benchmarks.
Published date:
17 May 2022
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
As governments around the world are committing to reaching net zero emissions by 2050, many countries are looking at the role hydrogen can play in mitigating climate change. This page provides more i...
Published date:
16 September 2022
The NEA nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.
Published date:
6 December 2023
Established to help fulfil the objectives of the Agency and the Nuclear Science Committee (NSC), the NSC Programme Review Group (PRG) formulates recommendations based on best practices to optimise ac...
Published date:
19 March 2024
NEA/NSC/R(2020)7
In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...
Published date:
2 December 2021
NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark
Published date:
2 August 2022
The aim of the benchmark is to improve understanding and modelling of pellet-cladding mechanical interaction (PCMI) amongst NEA member organisations. This is achieved by comparing PCMI predictions of...
Published date:
23 March 2022
This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...
Published date:
2 August 2022
PWR MOX/UO2 Core Transient Benchmark
Published date:
7 December 2022
Proceedings of the Second Specialists' Meeting on Shielding Aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) at CERN, Geneva, Switzerland on 12-13 October 1995.
Published date:
4 March 2024
More than 20 international experts gathered for the second meeting of the third phase of the TAF-ID project.
Published date:
21 December 2023
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
The webinar "Research and international dialogue in technology nuclear power - What role for Italy?", was held on 17- 18 November 2021.
Published date:
14 December 2021
The NEA Data Bank's first in-person course since the pandemic started was on FISPACT, an enhanced multi-physics platform for neutron, proton, alpha, deuteron or gamma particle interactions.
Published date:
27 June 2022
NEA/NSC/R(2021)1
This benchmark report has been compiled under the guidance of the NEA Working Party on Nuclear Criticality Safety (WPNCS) in the Subgroup on the Role of Integral Experiment Uncertainties and Covarian...
Published date:
30 January 2023
A number of tests with detail well documented neutronics and thermal-hydraulics measurements data have been performed at the Rostov Unit 2 (Rostov-2) nuclear power plant (NPP). The reactor type is a ...
Published date:
2 August 2022
20 -
23 September 2022
Facility for Rare Isotope Beams at Michigan State University, East Lansing, Michigan (USA)
The 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) is tentatively planned to be held in East Lansing, Michigan, USA, on 20-23 September 2022. The SATI...
Published date:
2 November 2021
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
22 April 2024 -
22 May 2024
Online training & in-person event on 20-22 May 2024 in Lucca, Italy
Published date:
21 December 2023
JEFF Nuclear Data Week promotes co-operation between experimentalists, evaluators, producers and end-users of nuclear data.
Published date:
19 December 2023
31 March 2025 -
3 April 2025
Madrid, Spain
The OECD Nuclear Energy Agency (NEA) and CIEMAT are co-organising the Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7). The workshop will be held in Mad...
Published date:
29 April 2024
Published date:
8 December 2021
NEA/NSC/R(2021)2
Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.
Published date:
16 December 2021
The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.
Published date:
10 January 2024
28 -
31 May 2024
INFN Laboratori Nazionali di Frascati, Frascati, Italy
Published date:
18 July 2023
Knowledge of basic nuclear physics data is essential for the modelling and safe operation of all types of nuclear facilities. The de facto international standard format, Evaluated Nuclear Data File 6...
Published date:
22 September 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
10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.
Published date:
19 June 2023
NEA/NSC/R(2020)8
The following report is issued by the WPEC Subgroup 27, which builds upon the work of the previous Subgroups 21 and 23, critically reviewing the gamma emission data and providing recommendations to i...
Published date:
1 February 2022
The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....
Published date:
18 January 2024
NEA/NSC/R(2023)9
The Expert Group on Innovative Structural Materials (EGISM) was created in 2008 under the auspices of the Nuclear Science Committee’s (NSC) Working Party on Scientific Issues of the Fuel Cycle (WPFC)...
Published date:
12 March 2024
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
6 September 2023 -
27 October 2023
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
Published date:
5 September 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
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
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 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
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
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:
2 August 2023
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
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
Co-organised with the UK Atomic Energy Authority, the course took place on 20-22 June 2023.
Published date:
24 July 2023
The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.
Published date:
14 June 2023
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
TVA Watts Bar Unit 1 Multi-Physics Benchmark
Published date:
19 July 2022
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
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
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
The Working Party on Multi-scale Modelling of Fuels and Structural Material for Nuclear Systems (WPMM) was established to deal with the scientific and engineering aspects of fuels and structural mate...
Published date:
6 December 2023
The Working Party on Nuclear Criticality Safety (WPNCS) deals with technical and scientific issues relevant to criticality safety. Specific areas of interest include (but are not limited to) investig...
Published date:
28 March 2024
Over its 25 years of existence, the working party has contributed many topics and has led advances in criticality safety studies.
Published date:
28 July 2022
The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...
Published date:
21 December 2023
The Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) studies advanced nuclear fuel cycles, including fuel cycle scenarios, innovative fuels and materials, separation chemistry, waste...
Published date:
8 February 2024
27 May 2024
INFN Laboratori Nazionali di Frascati, Frascati, Italy
Published date:
16 April 2024
The mission of the Expert Group of Shielding aspects of Accelerators, Targets and Irradiation Facilities (SATIF) has been completed. Its work initiated the SATIF workshops which keep on serving as in...
Published date:
5 March 2024
The expert group is responsible for managing the activities related to the High Priority Request List (HPRL) for nuclear data, in particular for guaranteeing that the entries are up-to-date and well-...
Published date:
20 September 2022
The expert group was established to develop a nuclear data structure definition that can meet the needs of a broad set of nuclear data users and providers.
Published date:
20 September 2022
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS) studies the needs associated with the transitio...
Published date:
25 January 2024
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Fuel Recycling and Waste Technology (EGFRW) focuses on the separation processes releva...
Published date:
25 January 2024
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Innovative Fuel Elements (EGIFE) conducts joint and comparative studies to identify te...
Published date:
8 February 2024
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Reactor Coolants and Components Technology (EGCoCoT) undertakes activities to collect,...
Published date:
25 January 2024
30 May 2022 -
3 June 2022
Conference Center Hotel Aquabella, Aix-en-Provence, France (in-person meeting)
Published date:
29 March 2022
22 -
26 May 2023
Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy + virtual option on ZOOM
Published date:
17 May 2023
19 -
23 May 2024
Lucca, Italy
Published date:
29 April 2024