Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
NEA-1696 IFPE/REGATE L10.3
last modified: 13-APR-2004 | catalog | new | search |

NEA-1696 IFPE/REGATE L10.3

IFPE/REGATE L10.3, FGR and Fuel Swelling during power transient at medium burn-up (SILOE reactor)

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1. NAME OR DESIGNATION:  IFPE/REGATE L10.3.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/REGATE L10.3 NEA-1696/01 Arrived 13-APR-2004

Machines used:

No specified machine
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3. DESCRIPTION

This experiment deals with the study of fission gas release and fuel swelling during power transient at medium burn up. The rod was base irradiated in a PWR and then re-irradiated in the test reactor SILOE in Grenoble France. Since the rod is initially a segmented rod. The refabrication process prior to loading in the test is minor. In particular, the rod is not purged of its fission gases following refabrication.
Segmented rod
  - UO2 4.5 % U5
  - Zy4 stress relieve
  - Pint 26 Bar
- Irradiation in PWR up to 47.415  MWd/kgM
  - Diameter measurement
  - Fission gas release measurement par non destructive Kr 85 gamma measurement : 1.5 %
- Experimental power ramp in SILOE :
  - Aquilon Device : 130 bar
  - Axial power profile determined by Zr95 gammascanning
  - Conditioning power step : 195 W/cm during 48 hours
  - 10 W/cm/mn up to 385 W/cm
  - duration of high power level : 1h30
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9. STATUS
Package ID Status date Status
NEA-1696/01 13-APR-2004 Arrived at NEADB
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10. REFERENCES
NEA-1696/01, included references:
- Christine Struzik:
REGATE L10, fission gas release and cladding diameter of UO2 rod
during and after a transient at Bu > 47 MWd/kg
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Released by:
Mrs. Christine STRUZIK
CEA/DEN/DEC
CE Cadarache
Bat. 315
13108 St PAUL-LEZ-DURANCE Cedex
FRANCE
  
Compiled by: J.A. Turnbull
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16. MATERIAL AVAILABLE
NEA-1696/01
SUMMARY.DOC  text file giving a description of the experiments
REGATE.HIS  Irradiation history for both Gravlines and Siloe irradiation
L10-3CHARACTERIZATION.DOC  Pre-char. of segment and irradiation conditions
L103CORR.ASC  File of oxide thickness versus rod length
L10-3DIAM.ASC  File of diameter measurements versus rod length
MICRO.ASC   EPMA measurements of Cs, Nd, O, Pu, U and Xe
L103corr.xls   corrosion
L10-3diam.xls   diameter
MICRO.L10-3.xls   EPMA data
QA Report for the REGATE experiment.doc  Description of data processing
Readme.txt    Readme file
1ST FILES
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: burnup, fission gas release, swelling, transients.