Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1549 IFPE/IFA-533.2.
last modified: 12-NOV-1997 | catalog | new | search |

NEA-1549 IFPE/IFA-533.2.

IFPE/IFA-533.2, Fuel Thermal Behaviour at High Burnup, Halden Reactor

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1. NAME OF EXPERIMENT

IFPE/IFA-533.2

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2. COMPUTERS

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Program name Package id Status Status date
IFPE/IFA-533.2 NEA-1549/01 Arrived 12-NOV-1997

Machines used:

Package ID Orig. computer Test computer
NEA-1549/01 Many Computers
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3. DESCRIPTION

After twelve years irradiation in the Halden Boiling Water Reactor two fuel rods (Rod 807 and Rod 808) were re-instrumented with fuel centre thermocouples and reloaded into the reactor in order to investigate the fuel thermal behaviour at high burnup. The fuel rods were pre-irradiated with four other rods in the upper cluster of IFA-409 (IFA=Instrumented Fuel Assembly) from May 1973 to June 1985. After base irradiation the four neighbouring rods were re-instrumented with pressure transducers and ramp tested in IFA-535.5 and IFA-535.6 providing useful data about fission gas release (FGR) presented in the Fuel Performance Database as well (Ref. 1). The two rods re-instrumented with fuel centre thermocouples have been irradiated as IFA-533.2 from April 1992. As the irradiation history of IFA-533.2 in the first months was very similar to the history of the ramp tests, the fuel temperature and FGR data measured in the different IFAs can complement each other, although the fuel-cladding gap sizes were slightly different and due to re-instrumentation the internal gas conditions were also dissimilar.

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9. STATUS
Package ID Status date Status
NEA-1549/01 12-NOV-1997 Masterfiled restricted
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10. REFERENCES
NEA-1549/01, included references:
- T. Johnsen, P. Dalene and H.P. Boehnsdalen: Fuel Thermocouples
Re-Instrumentation of Irradiated Rods HWR-314 (May 1991)
- T. Johnsen, P. Dalene and H.P. Boehnsdalen: Re-Instrumentation of Irradiated
Rods, (NOS 807 and 808) with Fuel Thermocouples, HWR-316 (February 1992)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. AUTHORS

OECD Halden Reactor Project

Institutt for Energiteknikk

P.O. Box 173

N-1751 HALDEN

Norway

 

Compilation: Cs. Gyori

 

Review: J.A. Turnbull

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16. MATERIAL AVAILABLE
NEA-1549/01
808_BASE.DAT History file rod 808 (IFA-409)
808r.DAT     History file rod 808R (IFA-533.2)
STARTUP1.DAT Records burnup 44.51 MWd/kgU02
STARTUP2.DAT Records burnup 44.86 MWd/kgU02
STARTUP3.DAT Records burnup 45.49 MWd/kgU02
STARTUP4.DAT Records burnup 46.17 MWd/kgU02
SCRAM1.DAT   Data of the 1st scram
SCRAM2.DAT   Data of the 2nd scram
SCRAM3.DAT   Data of the 3rd scram
PLOT\        Postscript format of the figures referred to in the summary file
READ.ME      Readme file
533-2.SUM    Summary file about the experiments
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: BWR reactors, burnup, experimental data, fission products, fuel elements, fuel pellets, fuel rods, thermal conductivity.