The aim of the IFPE is to provide, a comprehensive and well-qualified database for model development and validation of fuel performance codes. The data encompasses both normal and off-normal operation and include prototypic commercial irradiations as well as experiments performed in Material Testing Reactors.
To date about 1452 rods/samples from various sources encompassing BWR, AGR, PHWR, PWR, and VVER reactor systems have been included in the IFPE collection, maintained jointly by the NEA and the IAEA.
| Experiment package | Scenario | Experiment primary purpose | Fuel type | NEA package # |
| Full IFPE Collection, including the DATIF database software | Many | Many | Many | 1664 |
| AEAT-IMC (released March 1999, updated Jan. 2023) | temperature ramp | Fission Gas Release (FGR) | AGR | 1594 |
| AECL-CANDU elements irradiated in NRU (released Feb. 2000, updated Jan. 2023) | steady-state | Fission Gas Release (FGR) | PHWR | 1596 |
| AECL-CR EXP-BDL-406 (released June 2009, updated Jan. 2023) | steady-state | CANDU fuel | PHWR | 1841 |
| AEKI Experimental Database of E110 Claddings under Accident Conditions (released Feb. 2008, updated Jan. 2023) | Cladding mechanical properties | VVER | 1799 | |
| Belgonucleaire and SCK-CEN PRIMO (released May 2007, updated July 2009) | power ramp | Pellet Clad Mechanical Interaction (PCMI); MOX fuel | PWR / MOX | 1776 |
| Belgonucleaire Beznau-1 (released May 2008) | NPP operation + PIE | MOX fuel | PWR / MOX | 1788 |
| Belgonucleaire Beznau-1 (released Oct. 2011) | NPP operation + PIE | Fuel behavior for high Pu MOX | PWR / MOX | 1863 |
| Belgonucleaire GAIN programme (released March 2002, updated Jan. 2023) | steady-state + power ramp | Fuel behavior for Gd doped fuel | PWR | 1625 |
| BR-3/DOE High Burnup Fuel Rod Hot Cell Program (released Sep. 2003, updated Jan. 2023) | steady-state | High burn up (HBU) | PWR | 1560 |
| CANDU experiment FIO-130 (released June 2010, updated Jan. 2023) | LOCA transient | Fuel behaviour under LOCA | PHWR | 1858 |
| CANDU experiment FIO-131 (released April 2007, updated Jan. 2023) | LOCA transient | Fuel behaviour under LOCA | PHWR | 1783 |
| CANDU IRDMR experiments FIO-118 and FIO-119 (released April 2007, updated Jan. 2023) | power ramp | Rod dimensional response on power | PHWR | 1777 |
| CEA defect fuel experiments (released Feb. 2000, updated Jan. 2023) | steady-state | Fission gas release for defect fuel | PWR | 1615 |
| CEA defect fuel experiments: EDITH-MOX 01 (released June 2000) | steady-state | Fission gas release for defect fuel | PWR / MOX | 1615 |
| CEA/EDF/FRAMATOME Contact 1 & 2 (released March 1999, updated Jan. 2003) | steady-state | Fission Gas Release (FGR); thermal performance; clad creep | PWR | 1595 |
| CEA/EDF/FRAMATOME PWR and OSIRIS ramped fuel rods (released Feb. 2000, last update Jan. 2006) | power ramp | Pellet Clad Mechanical Interaction (PCMI) | PWR | 1622 |
| CNEA six power ramp irradiations with (PHWR) MOX fuels (released Oct. 2000) | power ramp | Pellet Clad Mechanical Interaction (PCMI) | PHWR / MOX | 1626 |
| DOE Fissile Materials Disposition Program (released Jan. 2007) | steady-state | Integral performance of WG MOX fuel | MOX | 1774 |
| Halden Cases for FUMEX-I (released Sep. 2003, updated Jan. 2023) | MANY | Benchmark Package | MANY | 1599 |
| Halden IFA-429 (released Nov. 1997) | power cycling + steady state | Gas absorption; Fission Gas Release (FGR); thermal behaviour; power cycling | PWR | 1546 |
| Halden IFA-432 (released June 1995, updated Jan. 1996) | steady-state | Fuel integral performance | BWR | 1488 |
| Halden IFA-507 (released Oct. 2004) | power ramp | Thermal performance | LWR | 1729 |
| Halden IFA-519.9 (released Oct. 2011, updated Nov. 2020) | power cycling + steady state | Fission Gas Release (FGR); High Burn-up Structure (HBS) formation | PWR | 1860 |
| Halden IFA-533.2 (released Nov. 1997) | steady-state + power ramp | Thermal performance | LWR | 1549 |
| Halden IFA-534.14 (released Nov. 2002, updated June 2005) | steady-state | Fuel grain size; Fission Gas Release (FGR) | PWR | 1684 |
| Halden IFA-535.5 &.6 (released Nov. 1997, updated Jan. 2023) | power ramp | Fission Gas Release (FGR) | BWR | 1548 |
| Halden IFA-562.1 (released Nov. 1997) | steady-state + power ramp | Thermal performance; Pellet Clad Mechanical Interaction (PCMI) | LWR | 1547 |
| Halden IFA-585 (released March 2008) | steady-state | Cladding creep | BWR & PWR | 1803 |
| Halden IFA-597 Hollow and solid MOX rods experiments (released October 2006) | steady-state with uprate | Pellet design effect on MOX fuel Fission Gas Release (FGR) | PWR / MOX | 1772 |
| Halden IFA-597.3 (released Nov. 2002, updated April 2003) | steady-state | Integral experiments data | BWR | 1685 |
| Halden IFA-629.1 (released Oct. 2011, updated Jan. 2023) | steady-state | Fission Gas Release (FGR); swelling | PWR / MOX | 1861 |
| Halden IFA-650 series, experiments 650.1 and 650.2 (released Oct. 2011) | LOCA transient | Qualification LOCA test rig | PWR | 1862 |
| Halden/IMC(UK) (released Dec. 2003, updated June 2006) | power ramp | Fuel swelling | AGR | 1705 |
| Halden/JAEA IFA 514/565 (released Feb. 2009, last update Jan. 2023) | steady-state | Fuel creep; Fission Gas Release (FGR) | MOX | 1778 |
| Halden/JAEA Power Ramp Tests of MOX Fuel Rods IFA-591 (released April 2007, last update Jan. 2023) | power ramp | Pellet Clad Mechanical Interaction (PCMI); Fission Gas Release (FGR) | MOX | 1773 |
| HATAC in Siloe reactor (released Nov. 2005, last update Nov. 2009) | steady-state + power ramp | Fission Gas Release (FGR); sweeping in rods | PWR | 1697 |
| High Burn-up Effects Programme (released Nov. 1997, last update Jan. 2023) | steady-state | High burn up (HBU) | LWR | 1510 |
| Idealised cases to illustrate the functional dependence of FGR predictions (released April 2004) | Idealized Modelling Cases | Benchmark Package | MANY | 1720 |
| INR Pitesti - RO-89 and RO-51 (released April 2002, updated Jan. 2023) | steady-state | Effect of fuel density on Fission Gas Release (FGR) | PHWR | 1645 |
| Kola-3 (released Sep. 1996, updated March 1999) | NPP operation + PIE | Fission Gas Release (FGR); rod elongation at PIE | VVER | 1532 |
| KOLA-3 MIR (released March 2006, updated Oct. 2011) | steady-state + power ramp | Fission Gas Release (FGR); thermal performance | VVER | 1766 |
| NFIR-1 data for rods irradiated in BR3 under different operating regimes (released March 2006) | steady-state | Fuel design on Fission Gas Release (FGR) | PWR | 1758 |
| Novovoronezh-5 VVER1000 fuel behaviour data (released March 2006, last update Jan. 2023) | NPP operation + PIE | Rod elongation at PIE | VVER | 1741 |
| NRU MT-4 and MT6A (released Nov. 2003) | LOCA transient | LOCA Ballooning and blockage of rod bundle | PWR | 1710 |
| NSRR/JAERI Behaviour under Reactivity Initiated Accident Conditions (released Feb. 2005) | RIA transient | Fuel behaviour under RIA | BWR | 1724 |
| REGATE L10.3 (released April 2004) | power ramp | Fuel swelling; Fission Gas Release (FGR) | PWR | 1696 |
| RISOE-1 (released March 2005) | steady-state + bump | Fission Gas Release (FGR) | LWR | 1634 |
| RISOE-2 (released Dec. 1995, updated April 2005) | power ramp | Fission Gas Release (FGR) | BWR | 1502 |
| RISOE-3 (released Sept. 1995, updated April 2005) | power ramp | Fission Gas Release (FGR) | BWR & PWR | 1493 |
| Siemens PWR rods irradiated in GINNA (released March 2000) | NPP operation + PIE | pellet design on Pellet Clad Mechanical Interaction (PCMI) | PWR | 1623 |
| SOFIT (released Nov. 1997, last update Jan. 2023) | steady-state | Thermal performance | VVER | 1310 |
| Studsvik DEFEX (released April 2008) | steady-state with clad primary defect | Secondary clad degradation | BWR | 1806 |
| Studsvik DEFEX-II (released April 2008) | steady-state with clad primary defect | Secondary clad degradation | BWR | 1807 |
| Studsvik DEMO-RAMP I & II - BWR (released March 2001) | power ramp | Pellet Clad Interaction (PCI) | BWR | 1597 |
| Studsvik INTER-RAMP BWR Project (released Nov. 1997) | power ramp | Failure operational limits | BWR | 1555 |
| Studsvik OVER-RAMP PWR Project (released Nov. 1997, updated March 2006) | power ramp | Pellet Clad Mechanical Interaction (PCMI) failure analysis | PWR | 1556 |
| Studsvik ROPE-1 (released April 2008, updated Jan. 2023) | lift-off at steady-state | Clad creep out at rod overpressure | BWR | 1722 |
| Studsvik ROPE-II PWR rod over pressure experiment (released April 2008) | lift-off at steady-state | Clad creep out at rod overpressure | PWR | 1723 |
| Studsvik STEED-I Stored Energy / Enthalpy Determination (released April 2008) | steady-state + scram | Stored energy determination | PWR | 1809 |
| Studsvik SUPER-RAMP BWR and PWR Programmes (released Nov. 1997, last update Jan. 2023) | power ramp | Pellet Clad Mechanical Interaction (PCMI) failure analysis | BWR & PWR | 1557 |
| Studsvik TRANS-RAMP I, II and IV (released April 2003) | power ramp | Pellet Clad Mechanical Interaction (PCMI) failure analysis | BWR & PWR | 1648 |
| TRIBULATION (released Nov. 1996, updated March 2002) | steady-state + power ramp | High burn up (HBU) | LWR | 1536 |
| US-PWR 16x16 LTA Extended Burnup Demonstration Program (released June 2005) | NPP operation + PIE | High burn up (HBU) | PWR | 1738 |
| Zaporoshye VVER1000 fuel behaviour data (released Oct. 2004, updated Jan. 2023) | NPP operation + PIE | Fission Gas Release (FGR) determination at PIE | VVER | 1677 |
- 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)
The OECD NEA Data Bank is an international centre of resources which aims to make scientific tools available to the nuclear science and technology community and to organise training courses. The Computer Program Services (CPS) of the Data Bank are in charge of:
See
