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NEA-1741 IFPE/NOVOVORONEZH. (Abstract last modified 29-JAN-2007)
1.
NAME OF EXPERIMENT - IFPE/NOVOVORONEZH. 2.
COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
NEA-1741/02 Many Computers
3.
DESCRIPTION - 9.
STATUS 10.
REFERENCES - 12.
PROGRAMMING LANGUAGE -NEA-1741/02: 15.
NAME AND ESTABLISHMENT - 16.
MATERIAL AVAILABLE -NEA-1741/02: 17.
CATEGORIES - Keywords: DATA BASE SYSTEMS, FUEL BEHAVIOUR, FUEL ELEMENTS, IRRADIATION, LOSS-OF-COOLANT ACCIDENT, TRANSIENTS
Program-name Package-ID Status
IFPE/NOVOVORONEZH NEA-1741/01 Obsolete
IFPE/NOVOVORONEZH-R1 NEA-1741/02 Arrived
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).
NEA-1741/01: 29-JAN-2007 Obsolete
NEA-1741/02: 29-JAN-2007 Arrived at NEADB
NEA-1741/02:
- 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)
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
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)
- Y. Integral Experiments Data, Databases, Benchmarks
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