2009
DOI: 10.1016/j.jnucmat.2008.12.156
|View full text |Cite
|
Sign up to set email alerts
|

CEA developments of new ferritic ODS alloys for nuclear applications

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
5

Citation Types

1
47
0

Year Published

2011
2011
2019
2019

Publication Types

Select...
8
1
1

Relationship

2
8

Authors

Journals

citations
Cited by 134 publications
(58 citation statements)
references
References 10 publications
1
47
0
Order By: Relevance
“…Research works performed during recent years have revealed that ODS (Oxide Dispersion Strengthened) steels are promising materials for fuel pin cladding in Sodium Fast Reactors [1,2]. It appears that the bcc ferritic-martensitic lattice allows for a high resistance to irradiation swelling up to a dose of around 150 displacements per atom (dpa) and nano-oxides significantly improve creep and tensile properties at high temperature (650°C) by blocking the dislocations motion.…”
Section: Introductionmentioning
confidence: 99%
“…Research works performed during recent years have revealed that ODS (Oxide Dispersion Strengthened) steels are promising materials for fuel pin cladding in Sodium Fast Reactors [1,2]. It appears that the bcc ferritic-martensitic lattice allows for a high resistance to irradiation swelling up to a dose of around 150 displacements per atom (dpa) and nano-oxides significantly improve creep and tensile properties at high temperature (650°C) by blocking the dislocations motion.…”
Section: Introductionmentioning
confidence: 99%
“…ODS steels are commonly prepared by high-energy mechanical alloying (MA) of a mixture of steel powder and Y 2 O 3 particles followed by a consolidation stage consisting of hot isostatic pressing (HIP) or hot extrusion (HE) [11,12]. The samples are then submitted to annealing around 1100 • C for 1-2 h. In the last years the attention has been focused on Spark Plasma Sintering (SPS), a novel pressure assisted consolidation technology characterized by high heating rate, low sintering temperature, and short isothermal time at sintering temperature [13,14].…”
Section: Introductionmentioning
confidence: 99%
“…Oxide dispersion strengthened (ODS) Ferritic steels (12-18 wt%Cr) offer great potential as fuel cladding in sodium-cooled fast reactors (SFR) [1][2][3]. Compared with austenitic steels, they exhibit an excellent resistance to swelling under irradiation thanks to their bcc structure [4].…”
Section: Introductionmentioning
confidence: 99%