NEA-1677 IFPE/ZAPOROSHYE-V1K.

1. NAME OF EXPERIMENT:  IFPE/ZAPOROSHYE-V1K.

3. DESCRIPTION

Fuel Assembly (FA) No.E0325 was operated in the first unit of Zaporozskaya NPP (Ukraine) during the fuel cycles 4-8 (VVER-1000). It was irradiated for 1142.1 effective days, to a burnup of 48.9 MWd/kgU on average for the whole FA and of 51.3 MWd/kgU in the "hottest" fuel rod. The maximum local linear power in a fuel rod was 290 W/cm. The average linear power for the whole operational period of FA varied within the limits of 71-266 W/cm. The operational conditions of FA corresponded to the four-years fuel cycle, both on duration of the operation and burnup of the fuel. After the base irradiation, the FA N. E-0325 was subjected to PIE in the hot cells of SSC NIIAR (Russian Federation).

The following information is provided:

- Pre-characterization data:
Fuel Pellet Material: UO2 and chemical analyses, Uranium isotopic composition U235, 4.4 wt%, Grain size: 3.4 - 5.8 micron
Cladding Material: Zr-1%Nb
Rod parameters: Total length: 3837 [+2.0, -2.0] mm, Fill gas, pressure: He, 2.0-2.5 Mpa, Fuel assembly length: 4570 [+1.0, -1.0] mm

- Irradiation histories
- Post irradiation examinations
- Burnup at the EOL
- Measurement of outer cladding diameter of irradiated fuel rods
- Fuel rod length measurement
- Fuel-to-cladding gap measurement
- Fission Gas Release

- B.A.Kanashov et. al.:
Change in geometrical parameters of VVER high burnup fuel rods under operation
conditions and transient testing
Proceedings of  "International Conference On Vver Fuel Performance
Modelling And Experimental Support" 1-5 October 2001,Albena,Bulgaria
- Letter describing the original data
- Yu. Bibilashvili et. al.:
Fission Gas Products Behaviour Modelling in the
START-3 Code for the WWER Fuel at High Burnup and Transient Conditions"
Proceedings of  "Third International Seminar On Vver Fuel Performance
Modelling And Experimental Support"
Pamporovo, Bulgaria, 4-8 October, 1999, p.194-199
- A.V. Smirnov et. al.:
"Geometrical parameters of the fuel rod claddings of the VVER-440
after 4 and 5 fuel cycles and VVER-1000 after 3 and 4 fuel cycles of operation"
Technical Committee Meeting on Fuel Behaviour under Transient and LOCA
conditions, Halden, Norway, 10-14 September 2001
- Letter from A.Medvedev explaning spiral-to-linear numbering correspondence
- D. Markov et. al. :
Validation of WWER-1000 Fuel Rod Efficiency at Operation during Four Fuel Cycles
Proceedings of  "Third International Seminar On Vver Fuel Performance,
Modelling And Experimental Support",
Pamporovo, Bulgaria, 4-8 October, 1999, p.147-152
- Solonin M. et al.:
WWER Fuel Performance and Material Development for Extended Burnup in Russia,
Proceedings of the Second International Seminar, WWER Reactor Fuel Performance,
Modelling and Experimental Support, 21-25April 1997, Sandanski, Bulgaria (Ibid.
[4] pp. 48-57)

15. NAME AND ESTABLISHMENT OF AUTHORS

The experimental results from PIE were supplied by:
A. Smirnov and B. Kanashov
NIIAR
Research Institute of Atomic Reactors
433510, Dimitrovgrad, Uljanovsk region
Russian Federation
  
The irradiation history files were supplied by:
V. Onoufriev and F. Sokolov
Division of Nuclear Fuel Cycle and Waste Management
IAEA, Wagramer Strasse 5,
P.O. Box 100
A-1400 VIENNA
Austria
  
Compilation and analyses:
D. Elenkov
Institute for Nuclear Research and Nuclear Energy
Bulgarian Academy of Science
Tzarigradsko Shaussee 72
SOFIA 1784
Bulgaria
  
Review: J.A. Turnbull and Grigori Khvostov

IFPEFullData.zip Excel tables: measurements results of rod diameter & gap
DOC\ Description and Word documents
README\ QA report, description of all files and technical specification
HISTORIES\ ***his.txt   Irradiation histories for rods 001 to 312
deltaD_E0325.txt dD=(Dplenum - Dmin) in microns measured after
end-of-irradiation
deltaL_E0325.txt Fuel rod elongation in [mm] measured after end-of-irradiation
gap_E0325.txt    Fuel-to-cladding diametrical gap in microns measured after
end-of-irradiation
FGR.txt          FGR versus rod average burnup
IFPEFullData.zip Excel tables: measurements results of rod diameter & gap
DOC\ Description and Word documents
README\ QA report, description of all files and technical specification
HISTORIES\ ***his.txt   Irradiation histories for rods 001 to 312
deltaD_E0325.txt dD=(Dplenum - Dmin) in microns measured after
end-of-irradiation
deltaL_E0325.txt Fuel rod elongation in [mm] measured after end-of-irradiation
gap_E0325.txt    Fuel-to-cladding diametrical gap in microns measured after
end-of-irradiation
FGR.txt          FGR versus rod average burnup
CORRESPONDANCE\ Additional information.doc