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

NEA-1548 IFPE/IFA-535.

IFPE/IFA-535, Fission Gas Release, Power Ramps, High Burnup Fuel

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1. NAME OF EXPERIMENT:  IFPE/IFA-535.5 and IFPE/IFA-535.6.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/IFA-535.5 NEA-1548/01 Arrived 12-NOV-1997
IFPE/IFA-535.6 NEA-1548/02 Arrived 12-NOV-1997

Machines used:

Package ID Orig. computer Test computer
NEA-1548/01 Many Computers
NEA-1548/02 Many Computers
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3. DESCRIPTION

In order to investigate the effect of fuel rod pressurization on  fission gas release (FGR) two power ramp tests were performed  with two pairs of re-instrumented high burnup fuel rods in the  Halden Boiling Water Reactor. The fuel rods identified with the  numbers 809, 810, 811 and 812 were base irradiated in the upper  cluster of the two-cluster test assembly IFA-409 from May 1973  to June 1985 up to the average burnup level of 43.4 MWd/kgUO2.  The neutron flux was monitored with vanadium neutron detectors  located at different axial and radial positions in the assembly,  but other parameters were not measured in this IFA (Instrumented  Fuel Assembly). After the base irradiation the fuel rods were  equipped with pressure transducers and clad elongation sensors  in order to monitor the rod internal gas pressure and the  mechanical behaviour during a slow and a fast power ramp in IFA- 535.5 and IFA-535.6 respectively.  

The re-instrumented rods were ramp tested in IFA-535.5 (rods 809  and 810) from November 1985 to February 1986, and in IFA-535.6  (rods 811 and 812) from December 1986 to May 1987. Both rigs were  loaded into separated high pressure loops simulating PWR  conditions thus minimizing the risk of cladding failure due to  large pressure difference. The on-line rod pressure and  consequently FGR monitoring made the observation of particular  phenomena related to power variation possible. Beyond the in pile  pressure monitoring, post irradiation examination (PIE) was  performed for rods 809 and 810 in support of calculated FGR.
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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-1548/01 12-NOV-1997 Arrived at NEADB
NEA-1548/02 12-NOV-1997 Arrived at NEADB
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10. REFERENCES
NEA-1548/01, included references:
- V.Tosi:
The Effect of Pressurisation on Fission Gas Release in High Burn-Up
BWR-Type Fuel Rods (IFA-535.5 - 6), HWR-198 (April 1987)
NEA-1548/02, included references:
- V.Tosi:
The Effect of Pressurisation on Fission Gas Release in High Burn-Up BWR-Type
Fuel Rods (IFA-535.5 - 6), HWR-198 (April 1987)
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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-1548/01
miscellaneous    mag tapeREAD.ME Information file                   MISTP
miscellaneous    mag tape535.SUM Summary about the experiments      MISTP
test-case data   mag tape809_BASE.DAT History file rod 809 (IFA-409)DATTP
test-case data   mag tape810_BASE.DAT History file rod 810 (IFA-409)DATTP
test-case data   mag tape811_BASE.DAT History file rod 811 (IFA-409)DATTP
test-case data   mag tape812_BASE.DAT History file rod 812 (IFA-409)DATTP
test-case data   mag tape809.DAT History file rod 809 in IFA-535.5  DATTP
test-case data   mag tape810.DAT History file rod 810 in IFA-535.5  DATTP
test-case data   mag tapeCOOL-5.DAT Coolant parameters in IFA-535.5 DATTP
test-case data   mag tape809_300H.DAT Data rod 809 in the 1st 300hrsDATTP
test-case data   mag tape810_300H.DAT Data rod 809 in the 1st 300hrsDATTP
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 tapeFIG4.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG5.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG6.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG7.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG8.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG9.PS Fig. in summary file (Postscript)  OUTTP

NEA-1548/02
miscellaneous    mag tapeREAD.ME Information file                   MISTP
miscellaneous    mag tape535.SUM Summary about the experiments      MISTP
test-case data   mag tape809_BASE.DAT History file rod 809 (IFA-409)DATTP
test-case data   mag tape810_BASE.DAT History file rod 810 (IFA-409)DATTP
test-case data   mag tape811_BASE.DAT History file rod 811 (IFA-409)DATTP
test-case data   mag tape812_BASE.DAT History file rod 812 (IFA-409)DATTP
test-case data   mag tape811.DAT History file rod 809 in IFA-535.6  DATTP
test-case data   mag tape812.DAT History file rod 810 in IFA-535.6  DATTP
test-case data   mag tapeCOOL-6.DAT Coolant parameters in IFA-535.6 DATTP
test-case data   mag tape811_300H.DAT Data rod 809 in the 1st 300hrsDATTP
test-case data   mag tape812_300H.DAT Data rod 809 in the 1st 300hrsDATTP
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 tapeFIG4.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG5.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG6.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG7.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG8.PS Fig. in summary file (Postscript)  OUTTP
test-case output mag tapeFIG9.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 gas release, fission products, fuel elements, fuel pellets, fuel rods, post-irradiation examination.