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 IFA-650 series, experiments 650.9, 650.10 and 650.11 (Cases for IAEA’s FUMAC, released April 2024) | LOCA transient | High burnup fuel LOCA testing | VVER, PWR | 1921 |
| 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)
See
