International Fuel Performance Experiments (IFPE) content

Ongoing

To date about 1452 rods/samples from various sources encompassing BWR, CAGR, PHWR, PWR, and VVER reactor systems have been included in the IFPE collection, maintained jointly by the NEA and the IAEA.

Data currently available

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 (updated November 2014)	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
IFPE/CANDU-FIO-130, CANDU experiment FIO-130 Fuel Behaviour under LOCA Conditions (released June 2010)	1 fuel element	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) (updated November 2009)	2 rods	PWR
Belgonucléaire and SCK-CEN PRIMO Ramped MOX Fuel Rod BD8 (updated July 2009)	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 October 2011)	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 October 2011)	9 rods	VVER

Halden irradiated IFA-519.9, three PWR rods irradiated to 90 MWd/kg UO2 (for FUMEX-III) (updated October 2011)	3 rods	PWR
Halden irradiated IFA-629.1, Two MIMAS MOX rods commercially irradiated to 25 Wd/kg oxide (for FUMEX-III) (updated October 2011)	2 rods	PWR
Halden irradiated IFA-650 series, LOCA testing, two experiments (for FUMEX-III) (updated October 2011)	1 rod	PWR
Belgonucleaire Beznau-1 PWR irradiated MOX Fuel Rod M510/D10 (for FUMEX-III) (updated October 2011)	1 rod	PWR

Archives available

Data requested

AGR FGR database from British Energy
HRP He/Ar/Xe gas flow, Nb doped fuel, IFA-504

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

Activities

results

Computer Program Services (CPS)

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:

the collection, testing and preservation of computer programs;

the controlled distribution of computer programs, nuclear data libraries, integral experiment data, handbooks, benchmarks, safety joint projects and legacy books to end-users; and

the organisation of trainings and workshops.

DATabase for IFpe (DATIF)

DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NEA and the IAEA.

See

Expert Group on Reactor Fuel Performance (EGRFP)

Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of present and future nuclear power systems.

Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS)

The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nuclear power systems.