Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects

NEA-1677 IFPE/ZAPOROSHYE-V1K.

last modified: 16-JAN-2023 | catalog | new | search |

NEA-1677 IFPE/ZAPOROSHYE-V1K.

IFPE/ZAPOROSHYE-V1K, Zaporoshye VVER1000 fuel behaviour data (4-8 cycles, Burnup about 50 MWd/kgUO2)

NAME, COMPUTER, PROBLEM, STATUS, REFERENCES, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

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1. NAME OF EXPERIMENT

IFPE/ZAPOROSHYE-V1K

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

Program name	Package id	Status	Status date
IFPE/ZAPOROSHYE-V1K	NEA-1677/02	Arrived	16-JAN-2023

Machines used:

Package ID	Orig. computer	Test computer
NEA-1677/02	Many Computers

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3. DESCRIPTION

Fuel Assembly (FA) No.Å-0325 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).

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9. STATUS

Package ID	Status date	Status
NEA-1677/02	16-JAN-2023	Masterfiled restricted

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10. REFERENCES

NEA-1677/02, included references:

- 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
- Operation Factor Data of Fuel Rods of Wwer-1000 Fuel Assembly ?0325
- 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)

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12. PROGRAMMING LANGUAGE(S) USED

No specified programming language

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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

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

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16. MATERIAL AVAILABLE

NEA-1677/02

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
***his.txt         Irradiation histories for rods 001 to 312 (linear numbering)
Excel tables      Measurements results of rod diameter & gap
Read.me            Readme file
QA Report for FA-E0325(WWER-1000).doc    QA report, description of all files and
technical specification
Summary.txt        Summary file
Additional information.doc

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17. CATEGORIES

Y. Integral Experiments Data, Databases, Benchmarks

Keywords: VVER type reactor, experimental data, fuel elements, fuel rods.