SYMPOSIA PAPER Published: 01 January 1994
STP23964S

Tensile Properties of Neutron Irradiated 316Ti and 15-15Ti Steels

Source

This paper deals with the tensile behavior of CW316Ti and CW15-15Ti Phénix fuel pin cladding. The tension tests were conducted on defueled tubes irradiated up to 115 dpa3 in the 400–640°C temperature range. Test temperature corresponds essentially to irradiation temperature. The results emphasize that, although irradiation induces a reduction of ductility, the failure always occurs with significant plastic deformation, even for the most highly irradiated cladding.

At irradiation temperatures below 560°C, the embrittlement of both steels is correlated to the swelling and thus to the occurrence of irradiation-induced voids; in this case, the failure is transgranular. In the high irradiation temperature range, a marked difference is observed between the two steels when the tests are conducted at the irradiation temperature, since the rupture is essentially intergranular on CW316Ti and transgranular on CW15-15Ti. The tensile properties of the CW15-15Ti cladding are better than those of CW316Ti because it swells less and is less prone to creep-like embrittlement.

Author Information

Fissolo, A
DTA/CEREM/DTM/SRMA
Lévy, V
DTA/CEREM/DTM/SRMA
Séran, JL
DTA/CEREM/DTM/SRMA
Maillard, A
DTA/CEREM/DTM/SRMA
Royer, J
DRN/DMT/SETIC Commissariat à l'énergie atomique, Centre d'Etudes de Saclay, GIF-SUR-YVETTE, France
Rabouille, O
DRN/DMT/SETIC Commissariat à l'énergie atomique, Centre d'Etudes de Saclay, GIF-SUR-YVETTE, France
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Details
Developed by Committee: E10
Pages: 646–663
DOI: 10.1520/STP23964S
ISBN-EB: 978-0-8031-5262-5
ISBN-13: 978-0-8031-1488-3