last modified: 19-MAR-1999 | catalog | categories | new | search |

NEA-1532 IFPE/KOLA-3.

IFPE/KOLA-3, WWER-440 Fuel Performance Data from KOLA-3 NPP, FGR

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1. NAME OF EXPERIMENT:  IFPE/KOLA-3.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/KOLA-3 NEA-1532/02 Arrived 19-MAR-1999

Machines used:

Package ID Orig. computer Test computer
NEA-1532/02 Many Computers
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3. DESCRIPTION

Two pre-characterised standard  WWER-440 Fuel Assemblies with the identification numbers FA-198 and  FA-222 were irradiated in the Kola-3 reactor for four and five fuel  cycles respectively. The operation of these two assemblies was successfully completed in 1990-1991 with assembly average burn-ups of 46.2 (FA-198) and 48.2 (FA-222) MWd/kgU.
The assemblies were manufactured in May, 1986 with the specific goal to validate fuel performance and design for WWER-440 High Burnup Fuel Cycles. The pre-characterisation of UO2 fuel pellets, cladding  material and fabrication procedures was carried out at the Russian Nuclear Fuel Company "Elemash" (Electrostal).
The PIE has covered all items of interest to fuel performance. In particular, cladding dimensions and mechanical properties, clad water side and fuel side oxidation, fission gas release, gas pressure and gaseous fractions in fuel rods were measured.
The fission gas release is recognised as an important aspect for the design of the WWER-440 high burnup fuel. The measurements on FGR show that in general the FGR was low, with measured average values of 0.9 and 2.2% after four and five years of base-load reactor operation, respectively. With reference to the overall and safety criteria, the observed FGR is rather normal for the operation conditions currently applied for WWER-440 four year fuel cycles and  should not lead to major feedback effects at the end of life by the  fuel temperature response to the FGR.
At present only data for corner rods 7 and 120, and diagonal rods 31 and 86 from both assemblies are available. Also, the PIE data are restricted to FGR measured by puncturing, rod internal pressure at the end-of-life and clad creep-down over the active part of the fuel. Further data will be added as they become available.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-1532/02 19-MAR-1999 Arrived at NEADB
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10. REFERENCES

     Proselkov V.N., Scheglov A.S.
     Initial Fuel Assembly Characteristics and Irradiation History
     for Two Fuel Assemblies, Irradiated for Four and Five
     Cycles at Kola NPS. INR RRC KI. N 32/1-136-95. 1995. 19 p.
     Appendix 27 p.
     In the Russian version the list of authors: Proselkov V.N.,
     Scheglov A.S., Ananiev A.Yu. et al.

     Volkov B. e.a. Comparative Analysis of WWER and PWR Fuel
     Behaviour to a Burnup of 18 MWd/kgUO2.HWR-541. OECD Halden
     Reactor Project. Dec. 1997.
NEA-1532/02, included references:
- Smirnov A.V. et al.: Experimental Support of VVER-440 Fuel Reliability and
Serviceability at High Burnup. In: Proc. of an international seminar "VVER
Reactor Fuel Performance, Modelling and Experimental Support". 7-11 Nov. 1994,
St.Konstantine, Varna, Bulgaria. Pp. 141-146.
- Lemehov S.E., Smirnov A.V, and Tsibulya V.A.: "Kola-3 High Burn-up Fuel
Validation Tests FA-198 and FA-222." Paper F-1.1 presented at the Enlarged
Halden Programme Meeting on High Burn-up Fuel Performance, Safety and
Reliability and Degradation of In-core Materials and Water Chemistry Effects,
Loen, Norway, 19 - 24 May 1996 (HPR-347/3)
- Smirnov A.V. et al.: The Peculiarities of the WWER-440 Fuel Behavior at
Higher Burnups. In: Proc. of the Second International Seminar "WWER Reactor
Fuel Performance, Modelling and Experimental Support" (299 p.). 21-25 April
1997, Sandanski, Bulgaria. Pp. 58-65.
- Smirnov A.V. et al.: Behaviour of WWER-440 and WWER-1000 Fuel in a Burnup
Range of 20-48 MWd/kgU. Ibid. [4]. Pp 40-46.
- 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)
- Scheglov A.S., Proselkov V.N.: Some Results of PIN-mod2 Code Verification.
Ibid. [4]. Pp. 174-176.
- Sidorenko V.D., Scheglov A.S.: Neutron-and Physics Characteristics of the
VVER Core which affect the operability of the Fuel Elements (pp. 502-504)
Translated from Atomic Energy 1993 v.74, iss.6, Pp.533-535.
- D. Elenkov and K. Lassmann:
The Development of the Transuranus-WWER Version
- K. Lassmann, J. van de Laar and D. Elenkov:
Analysis of RIA Accidents for WWER Reactors Employing The Transuranus Code
- M. Manolova et al.:
Validation of the Transuranus Code - WWER Version by the Updated KOLA-3 Data Set
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

        VNIINM
        St Rogov 5, P.O. Box 369
        123060 MOSCOW
        Russian Federation

        Kurchatov Institute (IRTM)
        Kurchatov Square
        123182 MOSCOW
        Russian Federation

        Compiled by: V. Novikov (VNIINM)

        Review: Klaus Lassmann
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16. MATERIAL AVAILABLE
NEA-1532/02
SUMMARY.KOL Summary of data from KOLA-3
198&001.INP 10 zone irr. hist. rod 1 FA-198
198&007.INP 10 zone irr. hist. rod 7 FA-198
198&014.INP 10 zone irr. hist. rod14 FA-198
198&022.INP 10 zone irr. hist. rod22 FA-198
198&031.INP 10 zone irr. hist. rod31 FA-198
198&041.INP 10 zone irr. hist. rod41 FA-198
198&052.INP 10 zone irr. hist. rod52 FA-198
198&058.INP 10 zone irr. hist. rod58 FA-198
198&069.INP 10 zone irr. hist. rod69 FA-198
198&075.INP 10 zone irr. hist. rod75 FA-198
198&086.INP 10 zone irr. hist. rod86 FA-198
198&096.INP 10 zone irr. hist. rod96 FA-198
198&105.INP 10 zone irr. hist.rod105 FA-198
198&113.INP 10 zone irr. hist.rod113 FA-198
198&120.INP 10 zone irr. hist.rod120 FA-198
198&126.INP 10 zone irr. hist.rod126 FA-198
222&001.INP 10 zone irr. hist. rod 1 FA-222
222&007.INP 10 zone irr. hist. rod 7 FA-222
222&014.INP 10 zone irr. hist. rod14 FA-222
222&022.INP 10 zone irr. hist. rod22 FA-222
222&031.INP 10 zone irr. hist. rod31 FA-222
222&041.INP 10 zone irr. hist. rod41 FA-222
222&052.INP 10 zone irr. hist. rod52 FA-222
222&058.INP 10 zone irr. hist. rod58 FA-222
222&069.INP 10 zone irr. hist. rod69 FA-222
222&075.INP 10 zone irr. hist. rod75 FA-222
222&086.INP 10 zone irr. hist. rod86 FA-222
222&096.INP 10 zone irr. hist. rod96 FA-222
222&105.INP 10 zone irr. hist.rod105 FA-222
222&113.INP 10 zone irr. hist.rod113 FA-222
222&120.INP 10 zone irr. hist.rod120 FA-222
222&126.INP 10 zone irr. hist.rod126 FA-222
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: VVER type reactor, burnup, experimental data, fission gas release, fission products, fuel elements, fuel pellets, fuel rods, fuel-coolant interactions, xenon.