Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1532 IFPE/KOLA-3.
last modified: 19-MAR-1999 | catalog | 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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9. STATUS
Package ID Status date Status
NEA-1532/02 19-MAR-1999 Masterfiled restricted
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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, Devold, H, Ryazantzev, E P, and Yakovlev, V V.: 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, 21-25 April
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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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. AUTHORS

VNIINM

St Rogov 5, P.O. Box 369

123060 Moscow

Russian Federation

 

Kurchatov Institute (IRTM)

Kurchatov Square

123182 Moscow

Russian Federation

 

Compilation: V. Novikov (VNIINM)

 

Review: Klaus Lassmann

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16. MATERIAL AVAILABLE
NEA-1532/02
198&001.INP 10 zone irradiation history rod 1 FA-198
198&007.INP 10 zone irradiation history rod 7 FA-198
198&014.INP 10 zone irradiation history rod14 FA-198
198&022.INP 10 zone irradiation history rod22 FA-198
198&031.INP 10 zone irradiation history rod31 FA-198
198&041.INP 10 zone irradiation history rod41 FA-198
198&052.INP 10 zone irradiation history rod52 FA-198
198&058.INP 10 zone irradiation history rod58 FA-198
198&069.INP 10 zone irradiation history rod69 FA-198
198&075.INP 10 zone irradiation history rod75 FA-198
198&086.INP 10 zone irradiation history rod86 FA-198
198&096.INP 10 zone irradiation history rod96 FA-198
198&105.INP 10 zone irradiation history rod105 FA-198
198&113.INP 10 zone irradiation history rod113 FA-198
198&120.INP 10 zone irradiation history rod120 FA-198
198&126.INP 10 zone irradiation history rod126 FA-198
222&001.INP 10 zone irradiation history rod 1 FA-222
222&007.INP 10 zone irradiation history rod 7 FA-222
222&014.INP 10 zone irradiation history rod14 FA-222
222&022.INP 10 zone irradiation history rod22 FA-222
222&031.INP 10 zone irradiation history rod31 FA-222
222&041.INP 10 zone irradiation history rod41 FA-222
222&052.INP 10 zone irradiation history rod52 FA-222
222&058.INP 10 zone irradiation history rod58 FA-222
222&069.INP 10 zone irradiation history rod69 FA-222
222&075.INP 10 zone irradiation history rod75 FA-222
222&086.INP 10 zone irradiation history rod86 FA-222
222&096.INP 10 zone irradiation history rod96 FA-222
222&105.INP 10 zone irradiation history rod105 FA-222
222&113.INP 10 zone irradiation history rod113 FA-222
222&120.INP 10 zone irradiation history rod120 FA-222
222&126.INP 10 zone irradiation history rod126 FA-222
Summary of data from KOLA-3
data-198.txt
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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.