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

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.

DOE WG-MOX Fuel Irradiation Experiment Irradiated at the Advanced Test Reactor (ATR) (released Jan. 2007)  2 cases  ATR 
JAEA Power Ramp Tests of MOX Fuel Rods IFA-591 (released Apr. 2007)  11 rods  ATR 
Halden irradiated IFA-432 (released Jan. 96)  5 rods  BWR 
Studsvik INTER-RAMP BWR Project (released Nov. 97)  20 rods  BWR 
Studsvik SUPER-RAMP BWR Sub-Programme (released Dec. 2000)  16 rods  BWR 
Studsvik DEMO-RAMP I - BWR (released Mar. 2001)  5 rods  BWR 
Studsvik DEMO-RAMP II - BWR (released Mar. 2001)  8 rods  BWR 
HRP IFA-597.3 rods 7, 8 and 9 (cladding degradation, FCT, FGR at Bu »60 MWd/kgUO2 (for FUMEX-II) (released Nov. 2002)  3 rods  BWR 
Studsvik TRANS-RAMP I - BWR (released Mar. 2003)  5 rods  BWR 
JAERI - NSRR - Behaviour of Irradiated BWR Fuel under Reactivity -Initiated-Accident Conditions, Tests FK-1, -2 and -3 (released Feb. 2005)  3 cases  BWR 
Studsvik DEFEX BWR fuel secondary defect formation as a consequence of primary defects (released April 2008)  11 rods  BWR 
Studsvik DEFEX-II DEMO BWR fuel primary defect and conditions leading to secondary failure of the cladding by hydriding (released April 2008)  2 rods  BWR 
Studsvik ROPE-I (1986-93), BWR, 4 rods, Ringhals, investigates clad creep-out (released April 2008)  3 rods  BWR 
LWR MOX Fuel Irradiation Tests - HBWR Irradiation with the Instrument Rig, IFA-514/565 (JAEA) (Updated Dec. 2011)  6 rods  BWR 
AEAT-IMC NFB 8 and 34 (released Mar. 99)  22 samples  CAGR 
IMC(UK) swelling data from ramping CAGR UO2 fuel in the Halden Reactor (updated June 2006)  13 rods  CAGR 
RISOE-III Fuel Performance Data from 3rd Risoe Fission Gas Release (released Sept. 95)  16 rods  LWR 
RISOE-II Fuel Performance Data from Transient Fission Gas Release (released Dec. 95)  15 rods  LWR 
Halden irradiated IFA-533.2 (released Nov. 97)  1 rod  LWR 
Halden irradiated IFA-562.1 (released Nov. 97)  12 rods  LWR 
Rods from the TRIBULATION programme  (updated Mar. 2002)  19 rods  LWR 
The High Burn-up Effects Programme (updated Dec. 2002)  81 rods  LWR 
HRP IFA-507 TF3 and TF5 (transient temperature during power increase) - FUMEX-II (release Oct. 2004)  6 rods  LWR 
RISOE-I Fission Gas Release from High-Burnup Water Reactor Fuel (released Mar. 2005)  11 cases  LWR 
HRP IFA-585, In-Reactor Creep Behaviour of Zircaloy-2 and Zircaloy-4 under Variable Loading Conditions (released March 2008)  2 rods  LWR 
IFE/OECD/HRP FUMEX-I cases 1-6 (released Sep. 2003)  6 rods  MANY 
Idealised cases to illustrate the functional dependence of FGR predictions (for FUMEX-II) (released Apr. 2004)  7 cases  MANY 
AECL-CANDU elements irradiated in NRU (released Feb. 2000)  36 rods  PHWR 
CNEA six power ramp irradiations with (PHWR) MOX fuels (released Oct. 2000)  5 rods  PHWR 
INR Pitesti - RO-89 and RO-51 CANDU fuel type in-reactor measurement of internal gas pressure (released Apr. 2002)  2 rods  PHWR 
CANDU IRDMR experiments FIO-118 and FIO-119 CANDU Fuel Behaviour under LOCA Conditions (released Apr. 2007)  7 rods  PHWR 
CANDU experiment FIO-131 Fuel Behaviour under LOCA Conditions (released Apr. 2007)  1 rod  PHWR 
EXP-BDL-406, performance of CANDU natural UO2 fuel (bundles AAH, GF, and XY) irradiated at low linear powers (30-40 kW/m) to burnups above 450 MWh/kgU (AECL-CR) (for FUMEX-III exercise) (released June 2009)  3 rods  PHWR 
Halden irradiated IFA-429 (released Nov. 97)  7 rods  PWR 
Halden irradiated IFA-535.5 &.6 (released Nov. 97)  4 rods  PWR 
CENG defect fuel experiments (released Feb. 2000)  8 rods  PWR 
Siemens PWR rods irradiated in GINNA (released Mar. 2000)  17 rodlets  PWR 
CEA failed PWR rods irradiated in SILOE: EDITH-MOX 01 (released June 2000)  1 rod  PWR 
Belgonucléaire GAIN programme - fabrication, irradiation and PIE of 4 ramped UO2-Gd2O3 fuel rods with Zr4 cladding, irradiated in BR3 PWR (50 GWd/tU for peak pellet) (released Mar. 2002)  4 rods  PWR 
CEA/EDF/FRAMATOME Contact 1 & 2 (updated Jan. 2003)  3 rods  PWR 
Studsvik TRANS- RAMP II - PWR (released Mar. 2003)  6 rods  PWR 
Studsvik TRANS- RAMP IV - PWR (released Mar. 2003)  7 rods  PWR 
HRP IFA-534.14 rods 18 and 19 ( EOL FGR and pressure, grains size of 22 and 8.5 micrometers and Bu » 52 MWd/kgUO2 (for FUMEX-II) (updated May 2003)  2 rods  PWR 
BR-3 High Burnup Fuel Rod Hot Cell Program (DOE/ET 34073-1, Vol. 1&2) (released Sep. 2003)  5 rods  PWR 
NRU MT-4 and MT6A LOCA simulation tests (released Dec. 2003)  33 rods  PWR 
REGATE L10.3, fission gas release and mechanical behaviour, power ramp in Siloe / Aquilon device, 47 MWd/kg (updated Apr. 2004)  1 rod  PWR 
US-PWR 16x16 LTA Extended Burnup Demonstration Program (released July 2005)  9 rods  PWR 
CEA/EDF/FRAMATOME PWR and OSIRIS ramped fuel rods (updated Jan. 2006)  4 rods  PWR 
Studsvik OVER-RAMP PWR Project (updated Mar. 2006)  39 rods  PWR 
NFIR-1 data for rods irradiated in BR3 under different operating regimes (released March 2006)  6 rods  PWR 
HATAC in Siloe reactor / Griffon device, fission gas release, Bu=40-50 MWd/kg (for FUMEX-II) (released October 2006)  2 rods  PWR 
Belgonucléaire and SCK-CEN PRIMO Ramped MOX Fuel Rod BD8 (released May 2007)  1 rod  PWR 
Studsvik ROPE-II PWR rod over pressure experiment (released April 2008)  6 rods  PWR 
Studsvik STEED-I Stored Energy / Enthalpy Determination (released April 2008)  2 rods  PWR 
Belgonucléaire Beznau-1 PWR irradiated MOX Fuel Rod M109/D3 (released May 2008)  1 rod  PWR 
Studsvik SUPER-RAMP PWR Sub-Programme (updated Oct. 2010)  28 rods  PWR 
HRP-IFA-597 Hollow and solid MOX rods experiments (released October 2006)  2 rods  PWR 
 VVER 
WWER rods from Kola-3 (released Mar. 99)  32 rods  VVER 
The SOFIT WWER fuel Irradiation Programme (updated Dec. 2002)  12 rods  VVER 
Zaporoshye VVER1000 fuel behaviour data (cycles 4-8 , Bu ~ 50 MWd/kgUO2) (released Oct. 2004)  312 rods  VVER 
Novovoronezh-5 VVER1000 fuel behaviour data (cycles 7-9, Bu ~47MWd/kg) (updated Jan. 2007)  317 rods  VVER 
AEKI Experimental Database of E110 Claddings under Accident Conditions (released Feb. 2008)  ~200 tests  ~200 samples  VVER 
IFPE/KOLA-3-MIR-RAMP, KOLA-3 + MIR test (temperature during ramp, FGR and pressure at EOL, Bu ~ 55 MWd/kgUO2) (for FUMEX-II) (updated Oct. 2010)  9 rods  VVER 
Halden irridiated IFA-519.9, three PWR rods irridiated to 90 MWd/kg UO2 (for FUMEX-III) (released Oct. 2010)  3 rods  PWR
Halden irridiated IFA-629.1, Two MIMAS MOX rods commercially irridiated to 25Wd/kg oxide (for FUMEX-III) (released Oct. 2010)  2 rods  PWR
Halden irridited IFA-650 series, LOCA testing, two experiments (for FUMEX-III) (released Oct. 2010)  1 rod  PWR
Belgonucleaire Beznau-1 PWR irradiated MOX Fuel Rod M510/D10 (for FUMEX-III) (released Oct. 2010)  1 rod  PWR 


Archives available

Data requested

Potential additional data to be requested for FUMEX-III

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)

Available publications on fuel behaviour

For more detailed information see also:

Related links


Contacts

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Last reviewed: 18 January 2012