NEA-1696 IFPE/REGATE L10.3

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

NAME, COMPUTER, PROBLEM, STATUS, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

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1. NAME OF EXPERIMENT

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. Rules for end-users are available here.

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

Machines used:

Package ID	Orig. computer	Test computer
NEA-1696/01	Many Computers

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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.

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9. STATUS

Package ID	Status date	Status
NEA-1696/01	13-APR-2004	Masterfiled restricted

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12. PROGRAMMING LANGUAGE(S) USED

No specified programming language

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15. 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

L103CORR.ASC      Oxide thickness versus rod length
L10-3DIAM.ASC     Diameter measurements versus rod length
L10-3diam.xls     Diameter
L103corr.xls      Corrosion
MICRO.ASC         EPMA measurements of Cs, Nd, O, Pu, U and Xe
MICRO.L10-3.xls   EPMA data
REGATE.HIS        Irradiation history for both Gravlines and Siloe irradiation
L10-3CHARACTERIZATION.DOC    Pre-characterisation of segment and irradiation
conditions
SUMMARY.DOC       Description of the experiments
QA Report for the REGATE experiment

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17. CATEGORIES

Y. Integral Experiments Data, Databases, Benchmarks

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