Nuclear fuel pellets and a fuel rod. Photo: US DOE
International Fuel Performance Experiments (IFPE) is a data collection on nuclear fuel performance experiments for the purpose of code development and validation.
The aim of the project is to provide a comprehensive and well-qualified database on Zr clad UO2 fuel for model development and code validation. The data encompasses both normal and off-normal operation and include prototypic commercial irradiations as well as experiments performed in Material Testing Reactors. This work is carried out in close co-operation and co-ordination between the NEA and the International Atomic Energy Agency (IAEA).
In 2023, the IFPE collection was enhanced by a complimentary tool: the DATIF software (DATabase for IFpe). DATIF increases the usability of the IFPE data collection by providing:
Advanced search capabilities
Ability to launch IFPE content directly from DATIF
Ability to isualise coverage of selected parameters within database (e.g., burnup, enrichment)
(Restricted access media)
Requesters of IFPE cite their "use case" - visualisation of dominant themes from 2018-2023
Acquisition of data through discussion and negotiation with originators;
Compilation of the data into a standard form and content as agreed by an expert group set up to supervise the work;
Peer review of the data by independent experts;
Integration and indexing of the data into the IFPE database, inclusion of all used reports in electronic form;
Distribution to interested parties and assistance where necessary in use of datasets.
Content of the IFPE database
The database has been limited to thermal reactor fuel performance, principally with standard product Zircaloy clad UO2 fuel, although the addition of advanced products with fuel and clad variants is not ruled out. Further, efforts are underway to include select fast reactor fuel performance datasets. Emphasis has been placed on including well-qualified data that illustrate specific aspects of fuel performance. Of particular interest to fuel modellers are data on: fuel temperatures, fission gas release (FGR), fuel swelling, clad deformation (e.g. creep-down, ridging) and mechanical interactions. Data on these issues are of great value if measured in-pile by dedicated instrumentation and in this respect, the IFPE Database is fortunate in having access to several diverse experiments. In addition to direct in-pile measurement, every effort is made to include PIE information on clad diameters, oxide thickness, hydrogen content, fuel grain size, porosity, Electron Probe Micro Analysis (EPMA) and X-ray Fluorescence (XRF) measurements on caesium, xenon, other fission product and actinides.
To date about 1452 rods/samples from various sources encompassing BWR, AGR, PHWR, PWR, and VVER reactor systems have been included. The full list of data is available on the dedicated webpage. If you wish to submit a request for specific packages, please follow the guidance; for the full collection, please submit your request to the NEA Data Bank - Computer Program Services.
AEKI/KFKI Atomic Energy Research Institute
Anatech International Corporation
Atomic Energy of Canada Ltd. (AECL) Chalk River Laboratories
Battelle Pacific North-West Laboratory (PNL)
British Energy (BE)
British Nuclear Fuels Ltd. (BNFL)
Comisión Nacional de Energía Atómica (CNEA)
Commissariat a l'Energie Atomique (CEA)
EC Institute for Transuranium (ITU)
Electricite de France (EdF)
Electric Power Research Institute (EPRI)
Fortum Power and Heat Oy (Fortum)
Halden Reactor Project (HRP)
Imatran Voima Oy (IVO)
Institute of Nuclear Research Pitesti (INR-Pitesti)
Institute for Nuclear Research and Nuclear Energy Sofia (INRNE Sofia)
Japan Atomic Energy Agency (JAEA)
Kurchatov Institute Moscow (INR RCC)
Research Institute of Inorganic Materials, Bochvar Institute (VNIINM)
Risoe National Laboratory
Scientific Research Institute for Atomic Reactors (SSCR RIIAR)