SFCOMPO 2.0 (Spent Fuel Isotopic Composition) is a relational database designed to facilitate the search and visualisation of experimental assay data of spent nuclear fuel.
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2 October 2020
MeshTal Viewer is a Java based software which can read mesh tallies output formats of several neutron transport codes and display them graphically.
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2 October 2020
IRPhE Handbook 2019 Edition - Contents
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30 September 2020
The Nuclear Science Committee (NSC), through its expert group, conducted a study on research and development (R&D) needs in nuclear science, held a workshop on R&D needs for current and future nuclea...
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30 September 2020
Historically, average discharge burn-ups in light water reactors (LWRs) have steadily increased with time as experience has accumulated and technological developments have progressed. The main benefi...
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30 September 2020
The Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors (LWRs) is an international high-visibility benchmark for unce...
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30 September 2020
The page describes the NEA's work on computing radiation dose and modelling of radiation-induced degradation of reactor components.
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30 September 2020
3-D Radiation Transport benchmarks dealt with scientific issues in the field of deterministic and stochastic methods and computer codes relative to three dimensional (3-D) radiation transport.
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30 September 2020
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...
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30 September 2020
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29 September 2020
NEA/NSC/R(2020)2
The present report provides a summary of the experiments analysed and consensuses reached by NEA WPEC Subgroup 41, including final recommendations based on all experimental data available at the time...
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28 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...
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28 September 2020
International Conference on Nuclear Data for Science and Technology
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28 September 2020
Sensitivities Viewer is a Java based software which can read sensitivities files and plot sensitivities profiles.
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25 September 2020
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...
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25 September 2020
International Workshop on Nuclear Data Evaluation for Reactor Applications (WONDER)
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23 September 2020
New NEA reports on nuclear data evaluation
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5 August 2020
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5 August 2020
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...
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22 July 2020
The NEA Annual Report 2019 provides an overview of the status of nuclear power in NEA member countries and illustrative descriptions of the Agency's activities and international joint projects. 2019 ...
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12 June 2020
U-Zr-O system miscibility gap in the liquid state. Source: Guéneau et al. Journal of Nuclear Materials 254 (1998), 158-174.
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5 May 2020
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5 May 2020
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7 April 2020
Source Convergence in Criticality Safety Analyses - Phase II: Guidance for Analysts
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24 March 2020
ICSBEP Guide to the Expression of Uncertainties
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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
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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...
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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.
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24 March 2020
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...
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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...
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24 March 2020
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23 March 2020
Thermal Scattering Law S(α,β): Measurement, Evaluation and Application
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13 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
Co-ordinated Evaluation of Plutonium-239 in the Resonance Region
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12 March 2020
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