last modified: 29-JAN-2007 | catalog | categories | new | search |

NEA-1741 IFPE/NOVOVORONEZH.

IFPE/NOVOVORONEZH, operation factor data of the Novovoronezh VVER-1000 fuel assembly 4108 rods

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1. NAME OF EXPERIMENT:  IFPE/NOVOVORONEZH.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/NOVOVORONEZH-R1 NEA-1741/02 Arrived 29-JAN-2007

Machines used:

Package ID Orig. computer Test computer
NEA-1741/02 Many Computers
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3. DESCRIPTION

FA-4108 was operated in the fifth unit of Novovoronezh NPP during fuel cycles 7 9 to an average fuel burn-up of approx. 47 MWd/kgU.

The irradiation histories of 317 fuel rods are presented where variables are given for 30 axial zones in the following forms:
Bu - local burn-up, MWd/kgU;
Ql - local heat rate, kW/m;
T - temperature of cladding inner surface, deg.C;
Ft - neutron fluence (x 10-22), n/s/cm2 (E > 0.1 MEv).
  
After irradiation, the assembly was shipped to the hot cells of NIIAR Dimitrovgrad where following measurements were made:
- Rod length
- Clad diameter
- Fuel - clad gap
  
A comparison of the measurements is made with FA-0325 irradiated in the Zaporozskaya VVER-1000 in report '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' by Smirnov et al. The report also contains a description of the measuring techniques and an assessment of the measurement errors.

The rod behaviour was modelled using the START-3 code and predictions for individual rods are included in the dataset.
NEA-1741/02
Revision 1 includes the coolant parameters (see "Pre-Characterisation" file).
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9. STATUS
Package ID Status date Status
NEA-1741/02 29-JAN-2007 Arrived at NEADB
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10. REFERENCES
NEA-1741/02, included references:
- 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
Presented at the IAEA Technical Committee Meeting on Fuel behaviour under
transient and LOCA conditions (Halden, Norway, 10 September - 14 September 2001)
- 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

Scientific Research Institute for Atomic Reactors (SSCR RIIAR)
Dimitrovgrad, Russian Federation
  
VNIIM, Moscow, Russian Federation
  
Dr. Medvedev and Dr. Bogatyr
A. A. Bochvar Institute, Moscow, Russian Federation
  
Dr. Georgiev
INRNE, Bulgaria
  
Review of the data: J.A. Turnbull
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16. MATERIAL AVAILABLE
NEA-1741/02
Summary of Novovoronezh 5 Dataset.doc   Summary of irradiation
Pre-characterization.doc   WORD file detailing pre-characterization
###PAR    Irradiation histories for each rod ### = 002 through 331 (317 rods)
PIE results: WORD file comparing PIE measurements with FA-0325 irradiated in
Zaporozskaya (A.V. Smirnov)
DATA_List.xls    list of PIE measurements taken on specific rods (Excel)
deltaD_0325_4108.xls    Diameter change for every rod measured (Excel)
deltaL_0325_4108.xls    Length change for each rod measured (Excel)
Gap_4108_0325.xls   Fuel/clad gap for each rod measured (Excel)
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: data base systems, fuel behaviour, fuel elements, irradiation, loss-of-coolant accident, transients.