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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
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
NEA Document
Primary Radiation Damage in Materials
NEA/NSC/DOC(2015)9

Primary Radiation Damage in Materials – Review of Current Understanding and Proposed New Standard Displacement Damage Model to Incorporate in Cascade Defect Production Efficiency and Mixing Effects

English Material science WPMM NSC Nuclear science Materials science Nuclear science EGPRD …
Published date: 26 February 2015
NEA Document
State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels
NEA/NSC/R(2015)5

State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels

English WPMM Nuclear science Materials science Material science NSC Nuclear science EGM2F …
Published date: 3 September 2015
Activity
WPMM Expert Group on Validation and Benchmarks of Methods (EGVBM)

The objectives of the expert group are to assess the accuracy and calculation time of the various first principle tools applied in the assessment of the properties of the nuclear materials; assess th...

Material science WPMM NSC Nuclear science Materials science EGVBM …
Published date: 5 March 2020