NEA-1696 IFPE/REGATE L10.3

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

NAME OR DESIGNATION, COMPUTER, DESCRIPTION, STATUS, REFERENCES, LANGUAGE, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION: IFPE/REGATE L10.3.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.

Program name	Package id	Status	Status date
IFPE/REGATE L10.3	NEA-1696/01	Arrived	13-APR-2004

Machines used:

No item found

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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 item found

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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.