scholarly journals Oxidation/Corrosion Behaviour of ODS Ferritic/Martensitic Steels in Pb Melt at Elevated Temperature

2014 ◽  
Vol 2014 ◽  
pp. 1-8 ◽  
Author(s):  
O. I. Yaskiv ◽  
V. M. Fedirko
Keyword(s):  
Fusion Reactor ◽  
Corrosion Behaviour ◽  
Oxide Dispersion Strengthened ◽  
Oxide Dispersion ◽  
Martensitic Steels ◽  
Good Adhesion ◽  
High Temperature Application ◽  
9Cr Steel ◽  
Corrosion Kinetics ◽  
Temperature Application

Lead-based melts (Pb, Pb-Bi) are considered as candidate coolants and spallation neutron targets due to their excellent thermophysical and nuclear properties. However, the corrosion of structural materials remains a major issue. Oxide dispersion strengthened (ODS) ferritic/martensitic steels are considered for high temperature application for both fission and fusion reactor concepts. The oxidation/corrosion kinetics in a static oxygen-saturated Pb melt at temperature of 550°C as well as the morphology and composition of scales formed on ferritic/martensitic Fe-9Cr-1.5W and ferritic Fe-14Cr-1.5W ODS steels have been investigated. Both materials showed homogeneous multiple, dense scales that consisted of typical combination of Fe3O4 as outer sublayer and (Fe,Cr)3O4 as inner sublayer. A nonuniform growth of inner oxide sublayers into the metal matrix as well as a good adhesion to the metal substrate is observed. With the prolongation of exposure from 240 to 1000 h, observed scales grow from 35 µm to 45 µm for ODS Fe-9Cr steel and from 40 µm to 60 µm for ODS Fe-14Cr steel with the thinning rates of 0,22 and 0,31 mm/year correspondingly. The mechanism of scales formation is discussed.

Development of Adapted Material Testing for Cold Pilgering Process of ODS Tubes

2013 ◽  
Vol 554-557 ◽  
pp. 2243-2251 ◽  
Author(s):  
Katia Mocellin ◽  
Esteban Vanegas ◽  
Yann de Carlan ◽  
Roland E. Logé
Keyword(s):  
Room Temperature ◽  
Kinematic Hardening ◽  
Oxide Dispersion Strengthened ◽  
Stress And Strain ◽  
Oxide Dispersion ◽  
Martensitic Steels ◽  
Uniform Loading ◽  
Cold Pilgering ◽  
Irradiation Level ◽  
Numerical Approaches

Development of fast-neutron sodium-cooled Generation IV reactors is resulting in extremely severe environment conditions for cladding tubes [1]. Both temperature and irradiation level will increase compared to the nowadays conditions. Due to their characteristics in irradiated environment, the oxide dispersion strengthened (ODS) ferritic and martensitic steels are natural candidate cladding materials[2]. However, they exhibit low deformation capabilities at room temperature, leading to problematic issues for forming such as pilgering. In order to improve the fabrication route for tubes, both metallurgical and numerical approaches can be conducted [3,4,5]. To reach predictive description of damage location and evolution, an adapated Latham and Cockoft model has been developed. This model is, of course, highly depending on the stress and strain prediction of the numerical model which itself is linked to the behavior law. In this work, we will describe an adapted material test developed in order to reproduce the cyclic, non uniform loading of the material during pilgering. An advanced cyclic beahvior law is introduced in the software. The model of Chaboche using 2 isotropic and 2 kinematic variables is chosen[6]. An inverse analysis procedure is used to identify both isotropic and kinematic hardening parameters. The results obtained using the identified behavior law are compared to both experimental observation and to other models including monotonic or cyclic laws identified on traditional test.

Creep Behavior and Microstructure of 8Cr Oxide Dispersion Strengthened Martensitic Steel

2010 ◽  
Vol 638-642 ◽  
pp. 2309-2314
Author(s):  
Kei Shinozuka ◽  
Hisao Esaka ◽  
M. Tamura ◽  
Hiroyasu Tanigawa
Keyword(s):  
Creep Deformation ◽  
Rolling Direction ◽  
Oxide Dispersion Strengthened ◽  
Oxide Dispersion ◽  
Martensitic Steels ◽  
Creep Tests ◽  
Nuclear Fusion Reactor ◽  
Ods Steel ◽  
Temperature Oxide ◽  
Ods Steels

In international thermonuclear experimental reactor (ITER), reduced activation ferritic/martensitic steels will be used for plasma-facing materials. However, it is necessary to raise the temperature of operation in order to elevate efficiency of electric power generation by using the material which is more excellent in strength at elevated temperature. Oxide dispersion strengthened (ODS) steels are promising candidate for high temperature materials of a nuclear fusion reactor. There are many reports that ODS steels show very high creep strength, but there are few reports on creep deformation mechanism. In this work, creep deformation behavior of 8 wt% Cr ODS steel was investigated. This ODS steel had high density of fine dispersed Y2Ti2O7 particles and -ferrite grains elongated along the hot-rolling direction. The creep curve showed a low creep strain rate until specimen ruptured. Vickers hardness of the gauge part of specimens in interrupted creep tests decreased with increasing the loading time. However, that of the grip part did not change significantly. Accordingly, although dynamic recovery occurred in the ODS steel, it had not affected the creep deformation rate.

R&D of oxide dispersion strengthened ferritic martensitic steels for FBR

1998 ◽  
Vol 258-263 ◽  
pp. 1745-1749 ◽  
Author(s):  
S. Ukai ◽  
T. Nishida ◽  
T. Okuda ◽  
T. Yoshitake
Keyword(s):  
Oxide Dispersion Strengthened ◽  
Oxide Dispersion ◽  
Martensitic Steels

High Temperature Strength of Three ODS Ferritic/ Martensitic Steels

2007 ◽  
Vol 345-346 ◽  
pp. 1011-1014 ◽  
Author(s):  
Han Ki Yoon ◽  
Akihiko Kimura
Keyword(s):  
High Temperature ◽  
Fusion Reactor ◽  
Martensitic Steel ◽  
Operating Temperature ◽  
Oxide Dispersion Strengthened ◽  
High Temperature Strength ◽  
Martensitic Steels ◽  
First Wall ◽  
Wall Structures ◽  
Interesting Approach

Oxide dispersion strengthened (ODS) materials is leading candidates for blanket/first-wall structures of the fusion reactor. ODS materials for structure application in fusion rector would allow to increase the operating temperature to approximately 650. Therefore, this work focused on the optimization of metallurgical features to improve high temperature strength and elongation through understanding of contents of Cr and Al. In the study, the three kinds of ODS steels such as 19Cr-ODS (K1), 13Cr-Al-ODS (K2) and 19Cr-Al-ODS (K4) with Y2O3 content of 0.37wt% have been produced. And tensile test were performed on three ODS ferritic/martensitic steel between RT, 300, 400 and 600Dispersion hardening represents an interesting approach to improve the mechanical properties at elevated temperature, as they are foreseen in the future fusion reactor It has been successfully demonstrated that it is possible to expanse the temperature range for the application of fusion reactor.

High Temperature Creep-Fatigue Design and Service Experience

2008 ◽  
Vol 1125 ◽  
Author(s):  
A-A. F. Tavassoli ◽  
B. Fournier ◽  
M. Sauzay
Keyword(s):  
High Temperature ◽  
Austenitic Stainless Steels ◽  
Oxide Dispersion Strengthened ◽  
Cyclic Softening ◽  
Fatigue Tests ◽  
Oxide Dispersion ◽  
Martensitic Steels ◽  
Fatigue Design ◽  
Creep Fatigue

ABSTRACTGeneration IV fission and future fusion reactors envisage development of more efficient high temperature concepts where materials performances under creep-fatigue hold the key to success. This paper presents extended experimental results obtained from creep, fatigue and creep-fatigue tests on the main structural materials retained for these concepts, namely: stainless steel type 316L(N), the conventional Modified 9Cr-1Mo martensitic steel and its low activation derivatives such as Eurofer steel, and their more advanced grades strengthened by oxide dispersion. It shows that the existing recommendations made in design codes adequately cover individual damage due to creep or fatigue but often fall short under combined creep-fatigue interaction. This is partly due to the difficulties of reproducing service conditions in laboratory. In this paper, results from tests performed on components removed from reactor, after long service, are used to refine code recommendations.Using the above combined assessment, it is concluded that there is good confidence in predicting creep-fatigue damage for austenitic stainless steels. For the martensitic steels the effects of cyclic softening and microstructure coarsening throughout the fatigue life need more consideration in creep-fatigue recommendation. In the long-term development of ferritic/martensitic oxide dispersion strengthened grades with stable microstructure and no cyclic softening, appears promising provided problems associated with their fabrication and embrittlement are resolved.

Corrosion behaviour of oxide dispersion strengthened iron-chromium steels in liquid lead at 973 K

2018 ◽  
Vol 69 (11) ◽  
pp. 1584-1596 ◽  
Author(s):  
Enrica Ricci ◽  
Donatella Giuranno ◽  
Giovanna Canu ◽  
Stefano Amore ◽  
Rada Novakovic
Keyword(s):  
Corrosion Behaviour ◽  
Oxide Dispersion Strengthened ◽  
Liquid Lead ◽  
Oxide Dispersion ◽  
Chromium Steels ◽  
Iron Chromium

Small Angle Neutron Scattering Study of Ferritic ODS Alloys

2014 ◽  
Vol 1004-1005 ◽  
pp. 335-339
Author(s):  
Li Zhang ◽  
Ji Luo ◽  
Tian Fu Li ◽  
Wei Wang ◽  
Rong Deng Liu ◽  
...  
Keyword(s):  
Neutron Scattering ◽  
Small Angle ◽  
Small Angle Neutron Scattering ◽  
Fusion Reactor ◽  
Oxide Dispersion Strengthened ◽  
Oxide Dispersion ◽  
Scattering Study ◽  
Ods Alloys ◽  
Neutron Scattering Study ◽  
Different Content

Small Angle Neutron Scattering (SANS) technique allows characterizing the nanomicrostructure of the ferritic Oxide Dispersion Strengthened (ODS) steels which are candidates for the structure material of fusion reactor and fast reactor. A SANS study of domestic ferritic ODS alloys are presented. The main objective is to study the evolution of the oxide dispersion nanoparticle during the different stages of the fabrication and different content.

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