Published 1980
| Version v1
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Programmes and experimental devices for fuel-cladding interaction study
Description
The study of fuel-cladding interaction is carried out on the one hand with whole pins, maximum length two meters and pre-irradiated in a reactor such as BR3 (Prisca experiment), on the other hand with short pins; in this latter case the best should be to make, in hot cell, short pins from long pins coming from power reactors (Fabrice experiment) As a matter of fact irradiation in experimental reactor takes time and is expensive to get the same dose
Availability note (English)
MF available from INIS under the Report Number.Abstract (French)
L'etude de l'interaction combustible-gaine est effectuee d'une part sur des crayons entiers, de longueur au plus egale a deux metres et preirradies dans des reacteurs tels que BR 3 (experiences PRISCA), d'autre part sur des crayons courts; dans ce dernier, cas, la solution d'avenir semble etre la refabrication, en cellule chaude, de petits crayons a partir de crayons longs provenant de reacteurs de puissance (experiences FABRICE). La preirradiation dans les reacteurs experimentaux est en effet longue et onereuse pour obtenir les doses equivalentes a celles des reacteurs de puissanceFiles
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Additional details
Additional titles
- Original title (French)
- Programmes et dispositifs experimentaux pour l'etude de l'interaction combustion gaine
Publishing Information
- Imprint Pagination
- 24 p.
- Report number
- CEA-CONF--5045
Conference
- Title
- French-Soviet meeting on load follow-on operating fuel pins.
- Dates
- 8 - 18 Jan 1980.
- Place
- Moscow, USSR.
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 11555427
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL PINS; FUEL-CLADDING INTERACTIONS; IN PILE LOOPS; IRRADIATION CAPSULES; IRRADIATION DEVICES; LOAD MANAGEMENT; PWR TYPE REACTORS
- Descriptors DEC
- FUEL ELEMENTS; MANAGEMENT; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS