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:
12 April 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 April 2023
5 -
6 June 2023
Oregon State University, Corvallis, Oregon, United States
Published date:
20 April 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:
4 May 2023
NEST Alumni share valuable lessons from their fellowships
Published date:
25 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
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
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
EGPRS Task Force members met on 3 April 2023.
Published date:
7 April 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
The WPRS met from 20-24 February 2023.
Published date:
17 March 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:
3 March 2023
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
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
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
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
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 with the go...
Published date:
21 November 2022
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
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
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:
2 June 2022
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:
17 May 2022
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:
24 February 2022
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:
23 February 2022
NEA/NSC/R(2021)2
Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.
Published date:
16 December 2021
Published date:
8 December 2021
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
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
Published date:
15 October 2021
Published date:
15 October 2021
The expert group critically reviewed integral experiments for validating minor actinide (MA) nuclear data, recommended additional integral experiments needed for validating MA nuclear data and invest...
Published date:
5 March 2021
NEA/NSC/R(2020)1
Since 2007, the NEA has organised a series of workshops on structural materials for innovative nuclear systems (SMINS). The fifth meeting, held from 8‑11 July 2019 in Kyoto, Japan, was hosted by Kyot...
Published date:
26 November 2020
The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors, requiring an increase in the total loading necessary in mixed plutonium-ura...
Published date:
17 November 2020
NEA/NSC/R(2019)3
The Nuclear Energy Agency (NEA) Expert Group on Liquid Metal Technology (EGLM) conducted a survey to identify and establish common criteria and understanding on the complex issue of materials data se...
Published date:
20 October 2020
Published date:
12 October 2020
Published date:
12 October 2020
NEA Nuclear Science Committee (NSC) meeting, 23-25 September 2020.
Published date:
9 October 2020
NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...
Published date:
1 October 2020
Published date:
29 September 2020
NEA/NSC/R(2020)3
The following report is issued by WPEC Subgroup 28, which builds upon the work of the previous Subgroup 20 for developing new methods for cross-section covariance evaluation. Subgroup 28 was tasked w...
Published date:
28 September 2020
New NEA reports on nuclear data evaluation
Published date:
5 August 2020
Source Convergence in Criticality Safety Analyses - Phase II: Guidance for Analysts
Published date:
24 March 2020
NEA/NSC/DOC(1995)3
Document content and format guide for the International Criticality Safety Benchmark Evaluation Project (ICSBEP) – NEA/NSC/DOC(95)03
Published date:
24 March 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality experiments are controlled tests using fissile materials, like pluton...
Published date:
24 March 2020
A criticality excursion (also referred to as a criticality accident) is the accidental production of a self-sustaining or divergent chain reaction of fissionable material.
Published date:
24 March 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality safety analysis relates to evaluation approaches in data and computat...
Published date:
24 March 2020
Thermal Scattering Law S(α,β): Measurement, Evaluation and Application
Published date:
13 March 2020
