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NEA-1493 IFPE/RISOE-III.

IFPE/RISOE-III, Fuel Performance Data from 3rd Risoe Fission Gas Release

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1. NAME OF EXPERIMENT:  IFPE/RISOE-III.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/RISOEIII NEA-1493/17 Arrived 19-SEP-1995

Machines used:

Package ID Orig. computer Test computer
NEA-1493/17 Many Computers
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3. DESCRIPTION

The Risoe National Laboratory in Denmark have carried out three irradiation programs of slow ramp and hold tests, so called 'bump tests' to investigate fission gas release and fuel microstructural changes. The third and final project which took place between 1986 and 1990 bump tested fuel re-instrumented with both pressure transducers and fuel centreline thermocouples.
The innovative technique employed for re-fabrication involved freezing the fuel rod to hold the fuel fragments in position before  cutting and drilling away the centre part of the solid pellets to accommodate the new thermocouple.
The fuel used in the project was from: IFA-161 irradiated in the Halden BWR (irradiation history provided) 13 to 46 MWd/kgUO2, GE BWR fuel irradiated in Quad Cities 1 and Millstone 1 20 to 40 MWd/kgUO2  and ANF PWR fuel irradiated in Biblis A to 38 MWd/kgUO2.
The data from the project are particularly valuable because of the in-pile data on fuel temperatures and pressures as well as extensive post irradiation examination (PIE). More specifically the tests are  characterized as follows:
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Test  Type  Burn-up  BTL    Fill Gas   Hold Time  Purpose
            % FIMA   kW/m               hours
------------------------------------------------------------------
AN1    P     4.4     39.8   15 bar He     42     Effect of
                                                 refabrication

AN2    U     4.3     39.0   25 bar He     62     Effect of power
                                                 history and
                                                 refabrication

AN3   TP     4.4     40.7   15 bar He     42     Effect of fill
                                                 gas and
                                                 refabrication

AN4   TP     4.4     40.7    1 bar Xe     42     Effect of fill gas

AN8    U     4.3     29.8   25 bar He      4     Power history,
                                                 fuel type and low
                                                 power FGR

AN10  TP     4.4     34.4    5 bar He     40     Power history,
                                                 low power FGR

AN11   U     4.4     16.9   25 bar He      4     Low power FGR

GE2   TP     4.21    40.5    5 bar He     41     Effect of burn-up
                                                 and power history

GE4   TP     2.4     43.3    5 bar He     34     Effect of burn-up
                                                 and fuel grain
                                                 size

GE6   TP     3.71    37.9    5 bar He    140     Power history

GE7    U     4.17    35.5    3 bar He      4     Power history and
                                                 fuel type

II1    T     4.8     40.3    1 bar Xe     24     Link to 2nd project

II2   TP     2.8     42.8    5 bar He      2     Link to 2nd project

II3   TP     1.6     44.7    5 bar He     36     Burn-up, link to
                                                 project

II5   TP     5.3     40.1    5 bar He     24     Burn-up, link to
                                                 2nd project
--------------------------------------------------------------------
Note:  BTL refers to Bump Terminal Level (Power)

       T = fuel centreline thermocouple, P = pressure transducer
       U = unopened

       ANx was a test with ANF PWR fuel irradiated in Biblis A
       GEx was a test with GE BWR fuel irradiated in Quad Cities 1
       II1 and II5 used fuel from HBWR irradiated IFA-161
       II2 and II3 used GE fuel irradiated in Millstone 1

Data sets identified as ANx stem from a test with ANF PWR fuel irradiated in Biblis A, those with GEx from a test with GE BWR fuel  irradiated in Quad Cities 1 II1 and II5 from tests with HBWR fuel irradiated in Halden (IFA-161) and II2 and II3 from tests with GE BWR fuel irradiated in Millstone 1.
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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-1493/17 19-SEP-1995 Arrived at NEADB
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10. REFERENCES
NEA-1493/17, included references:
- The Third Risoe Fission Gas Project Bump Test AN1 (CB9-2R)
RISOE-FGP3-AN1 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN2 (CB6)
RISOE-FGP3-AN2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN3 (CB8-2R)
RISOE-FGP3-AN3 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN4 (CB7-2R)
RISOE-FGP3-AN4 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN8 (CB10)
RISOE-FGP3-AN8 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN10 (CB13-4R)
RISOE-FGP3-AN10 (September 1990)
- The Third Risoe Fission Gas Project Bump Test AN11 (CB11)
RISOE-FGP3-AN11 (September 1990)
- The Third Risoe Fission Gas Project ANF Fuel (ANF-Data)
RISOE-FGP3-ANF,Pt.1 (September 1990)
- The Third Risoe Fission Gas Project ANF Fuel (Risoe-Data)
RISOE-FGP3-ANF,Pt.2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test GE2 (ZX114-3R)
RISOE-FGP3-GE2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test GE4 (XW104-3R)
RISOE-FGP3-GE4 (September 1990)
- The Third Risoe Fission Gas Project Bump Test GE6 (ZX113-4R)
RISOE-FGP3-GE6 (September 1990)
- The Third Risoe Fission Gas Project Bump Test GE7 (ZX115)
RISOE-FGP3-GE7 (September 1990)
- The Third Risoe Fission Gas Project GE Fuel (GE-Data)
RISOE-FGP3-GE, Pt.1 (April 1990)
- The Third Risoe Fission Gas Project GE Fuel (Risoe-Data)
RISOE-FGP3-GE, Pt.2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test II1 (M72-2-2R)
RISOE-FGP3-II1 (September 1990)
- The Third Risoe Fission Gas Project Bump Test II2 (STR024-2R)
RISOE-FGP3-II2 (September 1990)
- The Third Risoe Fission Gas Project Bump Test II3 (STR014-3R)
RISOE-FGP3-II3 (September 1990)
- The Third Risoe Fission Gas Project Bump Test II5 (M72-2-7R)
RISOE-FGP3-II5 (September 1990)
- The Third Risoe Fission Gas Project TU Final Report (1/3)
RISOE-FGP3-TU,Pt.1 (April 1992)
- The Third Risoe Fission Gas Project TU Final Report (2/3)
RISOE-FGP3-TU,Pt.2 (April 1992)
- The Third Risoe Fission Gas Project TU Final Report (3/3)
RISOE-FGP3-TU,Pt.3 (April 1992)
- The Third Risoe Fission Gas Project Final Report: The Project
RISOE-FGP3-FINAL,Pt.1 (March 1991)
- The Third Risoe Fission Gas Project Final Report: The Methods
RISOE-FGP3-FINAL,Pt.2 (March 1991)
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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

     Risoe National Laboratory
     P.O. Box 49
     DK-4000 ROSKILDE
     DENMARK

     Compilation: J.A. Turnbull, UK
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16. MATERIAL AVAILABLE
NEA-1493/17
PRECHAR.*.*  Precharacterization data for each test
BASEHIST.*.*  Base irradiation
TESTPOW.*.*  Linear heat rating
TEMP.*.*  For T-tests, measured fuel centreline temperatures
TFVPOW.*.*  For T-tests, selected values of temperature and power
PRESS.*.*  For P-tests, measured internal pressure
FGR.*.*  Fission gas release
PIE.*.*  PIE data for each test
EPMA.*.*  Measurement of retained xenon concentration (measured by EPMA)
MGx.*.*  Measurement of retained 137-Cs concentration
XRFx.*.*  Measurement of retained xenon concentration (measured by X-ray)
QIAx.*.*  Porosity measurements across pellet radius
MG.*  Microgamma scanning profiles across pellets
XRF.*  X-ray fluorescence profiles across pellets
Description of the data and readme file
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: experimental data, fission gas release, fission products, fuel elements, fuel pellets, fuel rods, fuel-cladding interaction, fuel-coolant interactions, helium, xenon.