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International Fuel Performance Experiments (IFPE) database

International Fuel Performance Experiments (IFPE) is a data collection of nuclear fuel performance experiments for the purpose of code development and validation.

Fuel studies Nuclear science Experiments EGRPF Databases Ancillary data Reactor physics …
Published date: 29 May 2024
Activity
FIDES-II Cross-Cutting Pillars

The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues. 

Fuel in nuclear safety Nuclear science Nuclear safety research Reactor fuel performance
Published date: 23 May 2024
Activity
Accelerated Testing of Materials in Capsules (AToMiC) - FIDES-II Joint ExpErimental Programme (JEEP)

AToMiC is dedicated to the understanding of microstructural evolution of fuel materials for use in higher temperature, GenIV type reactors.

Generation IV reactors Nuclear science FIDES Nuclear safety research Nuclear science …
Published date: 17 May 2024
Activity
High-Temperature Creep Testing (HITEC) - FIDES-II Joint ExpErimental Programme (JEEP)

HITEC is dedicated to addressing challenges in the development and safety assessment of advanced non-LWR NPPs (or ANLWRs).

Nuclear science FIDES Nuclear safety research Nuclear science Accident Tolerant Fuels Reactor fuel performance Safety research …
Published date: 17 May 2024
Activity
In-pile Creep Studies of ATF Cladding (INCA) - FIDES-II Joint ExpErimental Programme (JEEP)

The INCA experiments will provide comparative data on the irradiation induced creep of current Zr alloys and Cr coated samples

Nuclear science Experiments FIDES Nuclear science International co-operation Accident tolerant fuels …
Published date: 17 May 2024
Activity
Loss-of‑Coolant High Burnup (LOC–HBu) - FIDES-II Joint ExpErimental Programme (JEEP)

LOC-HBU is dedicated to the understanding of LWR fuel performance at high burnup under loss-of‑coolant accident (LOCA) conditions.

Nuclear science FIDES Nuclear science Reactor fuel performance
Published date: 17 May 2024
Activity
EGPRS Radiation transport and shielding
Published date: 15 May 2024
Activity
SINBAD - Shielding Integral Benchmark Archive and Database

The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.

Transport Experiments Radiation Databases Radiation transport and shielding Reactor physics Integral experiments Verification and validation Validation SINBAD Benchmark …
Published date: 13 May 2024
Activity
Nuclear Science Committee Programme Review Group (NSC PRG)

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...

NSC Nuclear science Nuclear science
Published date: 19 March 2024
Activity
WPFC Expert Group on Innovative Fuel Elements (EGIFE)

Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Innovative Fuel Elements (EGIFE) conducts joint and comparative studies to identify te...

Nuclear fuel WPFC Fuel studies NSC EGIFE Nuclear science EGIF Partitioning and transmutation Fuel cycle physics and chemistry …
Published date: 8 February 2024