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WPMM Expert Group on Multi-scale Modelling Methods (EGM3)

Under the guidance of the Nuclear Science Committee (NSC) and under the mandate of the Working Party on Multi-scale Modelling of Materials (WPMM), the scope of the Expert Group on Multi-scale Modelli...

Material science WPMM NSC Nuclear science Materials science EGM3 …
Published date: 4 March 2020
Event
International Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors
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...

Material science WPMM NSC Nuclear science Materials science …
Published date: 5 March 2020
Other
International Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors, 7-9 March 2017 - Announcement

Announcement for the nternational Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors, 7-9 March 2017

Material science WPMM NSC Nuclear science Materials science …
Published date: 5 March 2020
Other
Participants - Kick-off meeting preparation for the Framework for Irradiation Experiments (FIDES) Joint Experimental Programmes (JEEPs)

Kick-off meeting preparation for the Framework for Irradiation Experiments (FIDES) Joint Experimental Programmes (JEEPs) - List of participants

Material science Nuclear science Materials science
Published date: 27 February 2020
Other
NEA Framework for Irradiation Experiments (FIDES) flyer

NEA Framework for Irradiation Experiments (FIDES) flyer (October 2019)

Nuclear fuel Material science Nuclear science Materials science Experimental needs …
Published date: 10 January 2020
Joint project
Dragon Project

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...

Criticality safety Generation IV reactors Nuclear science Gas-cooled reactors Reactor physics …
Published date: 14 October 2022
Joint project
Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)

Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA

TCOFF Phases

First Phase (2017-2020)

The TCOFF project established a framework for the exchange of technical...

Nuclear science Fission products Fukushima Thermodynamic data Nuclear safety research Safety research …
Published date: 7 December 2022
Joint project
QUENCH-ATF project

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...

Nuclear science Nuclear safety research Joint project Accident Tolerant Fuels Accident tolerant fuels …
Published date: 1 April 2022
News
Internationally recognised thermodynamic data to advance nuclear materials knowledge

International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.

News brief Fuel studies Nuclear science Materials science Nuclear data Joint project Material science Thermodynamic data TAF-ID …
Published date: 24 February 2023
Joint project
Thermodynamics of Advanced Fuels – International Database (TAF-ID) public version

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...
Material science Fuel studies Nuclear science Materials science Thermodynamics Thermodynamic data Databases TAF-ID Codes and programs …
Published date: 23 February 2023
Joint project
Material science Structural materials Fuel studies Nuclear science Materials science Thermodynamic data TAF-ID …
Published date: 23 February 2023
Event
International School on Simulation of Nuclear Reactor Systems (SINUS)
1 - 23 May 2023
Online training & in-person event on 22-23 May 2023 in Bologna, Italy

The NEA will organise the first International School on Simulation of Nuclear Reactor Systems (SINUS) on the topic of Reactor single- and multi-physics simulations based on Light Water Reactor (LWR) ...

Nuclear science Education WPRS Nuclear science Reactor physics …
Published date: 20 February 2023
NEA Document
Statistical Tests for Diagnosing Fission Source Convergence and Undersampling in Monte Carlo Criticality Calculations
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...

Criticality safety Monte Carlo method Nuclear science Criticality WPNCS Nuclear science …
Published date: 17 February 2023
NEA Document
English Nuclear science Criticality WPNCS WPRS Multiphysics Reactor physics Multiphysics EGMUP Reactor physics Criticality safety NSC Nuclear science …
Published date: 23 February 2016
Subtopic
Thermal hydraulics and mechanics

Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...

Reactor physics Nuclear science Thermal hydraulics Verification and validation Verification Validation Benchmark Thermal hydraulics and mechanics Reactor physics …
Published date: 10 December 2020
Subtopic
Criticality safety

Criticality safety relates to accident prevention and protection from an uncontrolled nuclear fission chain reaction, or a criticality accident.

Criticality safety
Published date: 2 December 2019
Subtopic
Accident-tolerant fuels

Accident-tolerant fuels may offer opportunities to enhance the safety and competitiveness of commercial nuclear power plants.

Accident Tolerant Fuels
Published date: 16 December 2019
NEA Document
Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes
NEA/NSC/R(2015)9

Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...

English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Reactor physics Sodium-cooled reactor NSC EGPRS Nuclear science Benchmark …
Published date: 5 November 2015
NEA Document
International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume II: Benchmark results of phase I Void distribution
NEA/NSC/R(2015)4

The objective of the benchmark was twofold. First, the benchmark aimed to evaluate currently available computational approaches in an effort to understand the strengths and weaknesses of current ther...

English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark …
Published date: 24 June 2015
NEA Document
International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume III: Departure from nucleate boiling
NEA/NSC/R(2015)7

The need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...

English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
Published date: 2 October 2015