Published 1983 | Version v1
Book

Swelling of oxide dispersion strengthened ferritic alloys

  • 1. Centre d'Etude de l'Energie Nucleaire, Mol (Belgium)

Description

Oxide dispersion strengthened ferritic alloys with composition Fe-13Cr and Ti, Mo and TiO2 or Y2O3 addition, developed as canning materials for fast breeder reactors, have been neutron and electron irradiated. No swelling has been observed in specimens neutron irradiated at 695 and 736 K to 1027 n/m-2 (E > 0.1 MeV). Phase changes have been observed in these specimens as well as in specimens heat treated in parallel with the neutron irradiations. Swelling has been observed in electron irradiated specimens in the temperature range 643 to 823 K. Doping with helium has a strong influence on void swelling in this case. Changes in fabrication mode have only a minor influence. (author)

Additional details

Publishing Information

Publisher
British Nuclear Energy Society.
Imprint Place
London (UK)
ISBN
0 7277 0175 4
Imprint Title
Dimensional stability and mechanical behaviour of irradiated metals and alloys. V. 1
Imprint Pagination
223 p.
Journal Page Range
p. 91-94.

Conference

Title
Dimensional stability and mechanical behaviour of irradiated metals and alloys conference.
Dates
11-13 Apr 1983.
Place
Brighton (UK).