Assessment of a new fabrication route for Fe–9Cr–1W ODS cladding tubes-Reference-Cited by-同舟云学术

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Assessment of a new fabrication route for Fe–9Cr–1W ODS cladding tubes

Published:2012-09 Issue:1-3 Volume:428 Page:47-53
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Toualbi L.,Cayron C.,Olier P.,Malaplate J.,Praud M.,Mathon M.-H.,Bossu D.,Rouesne E.,Montani A.,Logé R.,de Carlan Y.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference22 articles.

1. CEA developments of new ferritic ODS alloys for nuclear applications

2. Present development status of EUROFER and ODS EUROFER for application in blanket concepts;Lindau;Fusion Eng. Des,2005

3. High Burnup Fuel Cladding Materials R&D for Advanced Nuclear Systems

4. R&D of ferritic-martensitic steel EP450 ODS for fuel pin claddings of prospective fast reactors, in: Proceedings of DIANA I workshop “Dispersion Strengthened steels for advanced nuclear applications”, Aussois (France) April 4–8;Nikitina;J. Nucl. Mater.,2012

5. The development and stability of Y–Ti–O nanoclusters in mechanically alloyed Fe–Cr based ferritic alloys

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3. The Irradiation Effects in Ferritic, Ferritic–Martensitic and Austenitic Oxide Dispersion Strengthened Alloys: A Review;Materials;2024-07-10

4. Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C;Journal of Nuclear Science and Technology;2023-10-19

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