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

NEA-1546 IFPE/IFA-429.

IFPE/IFA-429, Fission Gas Release, Thermal Behaviour U02 Fuel, Halden Reactor

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1. NAME OF EXPERIMENT:  IFPE/IFA-429.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/IFA-429 NEA-1546/01 Arrived 12-NOV-1997

Machines used:

Package ID Orig. computer Test computer
NEA-1546/01 Many Computers
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3. DESCRIPTION

PWR type fuel rods assembled in three axially separated clusters of six rods were irradiated in the Halden Boiling Water Reactor as IFA-429 from June 1975 to September 1990. The eighteen-rod assembly had been designed to investigate gas absorption, fission gas release (FGR) and thermal behaviour of UO2 fuel during both steady state operation period and rapid power transients. In order to achieve the objectives, two rods were instrumented with fuel centre line thermocouples (TFs)and nine rods were instrumented with null-balance gas pressure transducers (PFs) monitoring rod internal gas pressure. The assembly was instrumented with nine vanadium neutron detectors, one cobalt detector, inlet and outlet coolant thermocouples and an inlet coolant flow turbine as well.
This database contains the measured temperature history for one of the middle cluster rods up to the burnup level of 53 MWd/kgUO2 and the measured internal pressure data for three upper and three lower cluster steady-state irradiated fuel rods subjected to rapid power transients. Rationalized power histories are also presented for all the seven rods.
In order to study FGR two series of power ramps were induced in August 1985 and in March 1988 by movable neutron absorbing shield surrounding the fuel rod clusters. Manually initiated gas pressure measurements were performed during the testing sequence. The FGR and the gas diffusion coefficients calculated on the basis of the measured rod internal pressure data are tabulated as well. Due to slightly different design characteristics of the six investigated fuel rods, the comparison of FGR data at three different fuel densities (91% TD, 93% TD and 95% TD), at two different grain sizes (6 um and 17 um) and at two different fuel-cladding gap sizes (200 um and 360 um) are possible.
As the null-balance pressure transducers were not part of the automatic data acquisition system the rod internal gas pressure data set is limited. Only the pressure data measured at zero power during the base irradiation period, and the average value of the pressures measured during the two series of rapid power transients are tabulated. Calculated fission gas release (FGR) data are also presented.
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4. METHOD OF SOLUTION

As the measured parameters were recorded in every 15th minute of the fifteen-year irradiation time, the huge original test fuel data base is not applicable for model validation without any rationalization. Hence the data were reduced on the basis of power history condensation performed for each rod. For the condensed histories new irradiation time is calculated on the basis of the burnup. However, for the investigation of some phenomena the 15 min. data acquisition frequency is required. Therefore some data from selected irradiation periods are presented without any condensation.
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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-1546/01 12-NOV-1997 Arrived at NEADB
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10. REFERENCES

- W.H. Jens and P.A. Lottes:
  Analysis of Heat Transfer, Burn-out, Pressure Drop and Density
  Data for High Pressure Water
  ANL-4627 (1951)
NEA-1546/01, included references:
M.E.Cunningham,K.Svanholm:
Fission Gas Release from PWR-Type Rods in IFA-429 during Rapid and
Short Power Increases, HWR-159 (March 1986)
M.R.Smith, P.M.Crosby,J.M.Aasgaard,Y.Minagawa:
Fission Gas Release during a Second Series of Rapid Power Increases
on IFA-429 Rods at 40 GWD/TUO2, HWR-237 (April 1988)
H.Devold,H.Wallin:
PIE Results from the High Burnup Rods CD/CH (IFA-429) and Comparison with
with In-Pile Data, HWR-409 (October 1994)
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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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-1546/01
miscellaneous    mag tapeREAD.ME Information file                   MISTP
miscellaneous    mag tape429.SUM Summary about the experiment       MISTP
test-case data   mag tapeRODAB.DAT History file for Rod AB          DATTP
test-case data   mag tapeRODAD.DAT History file for Rod AD          DATTP
test-case data   mag tapeRODAH.DAT History file for Rod AH          DATTP
test-case data   mag tapeRODBC.DAT History file for Rod BC          DATTP
test-case data   mag tapeRODCB.DAT History file for Rod CB          DATTP
test-case data   mag tapeRODCD.DAT History file for Rod CD          DATTP
test-case data   mag tapeRODCH.DAT History file for Rod CH          DATTP
test-case data   mag tapeTFBC.27 Tab.th.couple readings at27kW/m rodDATTP
test-case data   mag tapeTFBC.BU Tab.th.couple read. 4 burnup levelsDATTP
test-case data   mag tapePF429.DAT Press.data of 6 rods (zero power)DATTP
test-case data   mag tapePFBOL.DAT Press.data of 6 rods at BOL      DATTP
test-case data   mag tapeFGR.DAT Tab.data of Fission Gas Release    DATTP
test-case output mag tapeFIG1.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG23.PS Figure of summary file(Postscript)OUTTP
test-case output mag tapeFIG4.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG5.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG6.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG7.PS Figure of summary file(Postscript) OUTTP
test-case output mag tapeFIG8.PS Figure of summary file(Postscript) OUTTP
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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