Published 1993 | Version v1
Report Open

Influence of irradiation on the iodine-induced stress corrosion cracking behaviour of zircaloy

Creators

  • 1. CEA Centre d'Etudes de Grenoble, 38 (France). Dept. de Thermohydraulique et de Physique
  • 2. Fragema, 69 - Lyon (France)

Description

In this article we present the experimental device of internal pressurization and the results on stress-relieved zircaloy non irradiated and irradiated during a PWR cycle. The parameters evolution, in function of irradiation dose, is analyzed and the metallurgical parameters influence is evoked. 4 figs., 17 refs

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Additional titles

Original title (French)
Influence de l'irradiation sur le comportement du zircaloy en corrosion sous contrainte par l'iode

Publishing Information

Imprint Pagination
11 p.
Report number
CEA-CONF--11797

Conference

Title
12. International Conference on Structural Mechanics in Reactor Technology.
Original Conference Title
Actes du Congres SMIRT 12
Dates
15-20 Aug 1993.
Place
Stuttgart (Germany).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
25074099
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL CANS; IODINE; IRRADIATION; PWR TYPE REACTORS; RADIATION DOSES; STRESS CORROSION; TESTING; ZIRCALOY 4
Descriptors DEC
ALLOY-ZR98SN-4; ALLOYS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION; CORROSION RESISTANT ALLOYS; ELEMENTS; ENRICHED URANIUM REACTORS; HALOGENS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; MATERIALS; NONMETALS; POWER REACTORS; REACTORS; THERMAL REACTORS; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS