Published date:
20 December 2013
Co-ordinated Evaluation of Plutonium-239 in the Resonance Region
Published date:
12 March 2020
U-238 Capture and Inelastic Cross-Sections
Published date:
1 January 1999
Thermal Scattering Law S(α,β): Measurement, Evaluation and Application
Published date:
13 March 2020
Plutonium-239 Fission Cross-section Between 1 and 100 keV
Published date:
1 January 1996
Delayed Neutron Data for the Major Actinides
Published date:
11 October 2002
Subgroup 7 of the NEA Working Party on International Nuclear Data Co-operation (WPEC) was established to re-evaluate the nuclear data standards cross-section. These cross-section data are the basis f...
Published date:
29 November 2006
Present Status of Minor Actinide Data
Published date:
1 January 1999
This report has been prepared by Subgroup 9 which was set up in 1998 with the aim of investigating discrepancies found between microscopic and macroscopic data for the uranium-235 fission neutron spe...
Published date:
15 July 2003
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
Published date:
1 January 1998
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
International Workshop on Nuclear Data Evaluation for Reactor Applications (WONDER)
Published date:
23 September 2020
7 -
9 March 2017
OECD Conference Centre, 2 rue André Pascal, Paris, France
Advanced techniques for fuel modelling have progressed considerably in the last decade in part aided due to progress in high-performance computational capability. At the engineering scale, this has r...
Published date:
5 March 2020
Announcement for the nternational Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors, 7-9 March 2017
Published date:
5 March 2020
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
Published date:
29 July 2015
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
Published date:
1 January 1999
IRPhE Handbook 2019 Edition - Contents
Published date:
30 September 2020
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
JEF-2.2 Radioactive Decay Data; NEA Data Bank (August 1994).
Published date:
1 January 1994
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
Conditions for release, rules and restrictions applying to the Kalinin Unit 3 (Kalinin-3) Transient Benchmark caused by the switching-off of one of the four operating main circulation pumps (MCPs) at...
Published date:
30 September 2020
3 -
5 September 2019
OECD Conference Centre, CC15, 2 rue André Pascal, 75016, Paris, France
The continued evolution of fuel and materials technology, fuel performance, optimisation of operational limits, material ageing, failure limits, etc. requires experimental evidence obtained from test...
Published date:
27 February 2020
Published date:
1 January 1999
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
Nuclear materials science investigates how corrosion, irradiation, thermal ageing and mechanical load may affect materials properties and potentially degrade their performance.
Published date:
10 March 2020
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 is a Java based software which can read mesh tallies output formats of several neutron transport codes and display them graphically.
Published date:
2 October 2020
MeshTal Viewer user manual
Published date:
25 November 2022
This publication provides an introduction to minor actinide nuclear properties and discusses some of the arguments in favour of minor actinide recycling, as well as the potential role of thermal reac...
Published date:
18 November 2013
Published date:
21 June 2007
Published date:
13 July 2009
Published date:
25 May 2009