International Fuel Performance Experiments (IFPE) database
The public domain database on nuclear fuel performance
experiments for the purpose of code development and validation
The aim of the project is to provide in the public domain, 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,
Activities
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.
Composition of the IFPE database
The database is restricted 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. 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.
Data currently available
To date datasets about 1452 rods/samples from various sources
encompassing BWR, CAGR, PHWR, PWR, and VVER reactor systems have been
included.
Potential additional data to be requested for FUMEX-III
IFA-651 (MOX) : Three IMF rods, Two MOX-ATT rods (PSI/KAERI) and one MOX-SBR rod (BNFL). TF and PF in the BNFL rod. Irradiation of IFA-651.1 started in June 2000 and ended May 2003 (one IMF rod unloaded).
IFA-550 (Nb fuel): IFA-550.4 (Dec 1989 - Jan 1990) and IFA-550.5 (April - May 1990) relevant loadings for Nb-doped fuel testing
Contributing organisations
- AEA Technology
- AEKI/KFKI Atomic Energy Research Institute
- Anatech International Corporation
- AREVA NP
- Atomic Energy of Canada Ltd. (AECL) Chalk River Laboratories
- Battelle Pacific North-West Laboratory (PNL)
- Belgonucleaire
- British Energy (BE)
- British Nuclear Fuels Ltd. (BNFL)
- Comision Nacional d'Energia Atomica (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)
- SCK-CEN Mol
- Siemens Power Corporation
- Studsvik AB
- Swedish Nuclear Power Inspectorate (SKI)
- TVEL - Joint Stock Company, Moscow
- UK Health and Safety Executive
- UK Industry Management Committee (IMC)
- US Department of Energy(DOE)
Thermal Performance of High Burn-Up LWR Fuel Seminar
Proceedings, Cadarache, France, 3-6 March 1998, 389 pages, ISBN:
92-64-16957-1 (OECD bookstore) Executive
Summary
Fission Gas Behaviour in Water Reactor Fuels Seminar
Proceedings, Cadarache, France, 26-29 September 2000, 564 pages, ISBN:
92-64-19715-X (OECD bookstore) Executive
Summary