last modified: 12-NOV-1997 | catalog | categories | new | search |

NEA-1549 IFPE/IFA-533.

IFPE/IFA-533, 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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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-1549/01 12-NOV-1997 Arrived at NEADB
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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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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. ESTABLISHMENT OF AUTHORS

   OECD Halden Reactor Project
   Institutt for Energiteknikk
   P.O. Box 173
   N-1751 HALDEN
   Norway

   Compilation: Cs. Gyori

   Review: J.A. Turnbull, UK
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16. MATERIAL AVAILABLE
NEA-1549/01
miscellaneous    mag tapeREAD.ME Information file                   MISTP
miscellaneous    mag tape533-2.SUM Summary about the experiments    MISTP
test-case data   mag tape808_BASE.DAT History file rod 808 (IFA-409)DATTP
test-case data   mag tape808r.DAT History file rod 808R (IFA-533.2) DATTP
test-case data   mag tapeSTARTUP1.DAT Records burnup 44.51 MWd/kgU02DATTP
test-case data   mag tapeSTARTUP2.DAT Records burnup 44.86 MWd/kgU02DATTP
test-case data   mag tapeSTARTUP3.DAT Records burnup 45.49 MWd/kgU02DATTP
test-case data   mag tapeSTARTUP4.DAT Records burnup 46.17 MWd/kgU02DATTP
test-case data   mag tapeSCRAM1.DAT Data of the 1st scram           DATTP
test-case data   mag tapeSCRAM2.DAT Data of the 2nd scram           DATTP
test-case data   mag tapeSCRAM3.DAT Data of the 3rd scram           DATTP
test-case output mag tapeFIG1.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG2.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG3.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG45.PS Fig. in summary file (Postscript) OUTTP
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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.