Vacancy Type Defects in Oxide Dispersion Strengthened Steels

2012 ◽  
Vol 733 ◽  
pp. 264-269
Author(s):  
Vladimir Slugeň ◽  
Jana Veterníková ◽  
Jarmila Degmová ◽  
S. Kilpeläinen ◽  
F. Tuomisto ◽  
...  

This study was focused on commercial oxide-dispersion strengthened (ODS) steels - MA 956 (20%Cr), PM 2000 (19%Cr), ODM 751 (16%Cr) and MA 957 (14%Cr) developed for fuel cladding of GEN IV reactors. The ODS steels are described in order to comparison of their microstructure features. Vacancy defects were observed by Doppler Broadening Spectroscopy (DBS) and Positron Annihilation Lifetime Spectroscopy (PALS). Residual stress proportional to all kinds of defects was investigated by Magnetic Barkhausen Noise (MBN) measurement. The highest presence of open volume defects was found in MA 956 and the lowest defect concentration in MA 957, although this steel contains the largest defects (six-vacancies together with dislocations). Other investigated steels demonstrated probably three- or four-vacancy clusters. Further, results from positron technique indicated proportionality of chromium content to defect concentration. Magnetic Barkhausen noise results also showed that Hpeak value (describing grain size) increased with growth of chromium content. However residual stress was independent on chromium level.

2012 ◽  
Vol 35 ◽  
pp. 98-103 ◽  
Author(s):  
V. Slugeň ◽  
J. Veterníková ◽  
S. Kilpeläinen ◽  
F. Tuomisto

2017 ◽  
Vol 68 (7) ◽  
pp. 62-65
Author(s):  
Jana Simeg Veternikova ◽  
Martin Fides ◽  
Jarmila Degmova ◽  
Stanislav Sojak ◽  
Martin Petriska ◽  
...  

AbstractThree oxide dispersion strengthened (ODS) steels with different chromium content (MA 956, MA 957 and ODM 751) were studied as candidate materials for new nuclear reactors in term of their radiation stability. The radiation damage was experimentally simulated by helium ion implantation with energy of ions up to 500 keV. The study was focused on surface and sub-surface structural change due to the ion implantation observed by mostly non-destructive techniques: positron annihilation lifetime spectroscopy and nanoindentation. The applied techniques demonstrated the best radiation stability of the steel ODM 751. Blistering effect occurred due to high implantation dose (mostly in MA 956) was studied in details.


2022 ◽  
Vol 25 ◽  
Author(s):  
Marcel Freitas de Souza ◽  
Juan Manuel Pardal ◽  
Hugo Ribeiro da Igreja ◽  
Linilson Rodrigues Padovese ◽  
Maria Cindra Fonseca

2014 ◽  
Vol 996 ◽  
pp. 373-379 ◽  
Author(s):  
Aitor Lasaosa ◽  
Kizkitza Gurruchaga ◽  
Virginia García Navas ◽  
Ane Martínez-de-Guereñu

The use of magnetic Barkhausen noise (MBN) signal to non-destructively characterize the in-depth residual stress state of machined steel was investigated. The effect of the frequency of the magnetic field applied and of analysing the resulting MBN signal in different frequency bands for an in-depth residual stress characterisation is discussed. The effect of the residual stress on each of the parameters derived from the MBN signal is analysed comparing with the result of the XRD method.


Measurement ◽  
2021 ◽  
Vol 168 ◽  
pp. 108473
Author(s):  
Haijiang Dong ◽  
Xiucheng Liu ◽  
Yahu Song ◽  
Bo Wang ◽  
Shenglai Chen ◽  
...  

2016 ◽  
Vol 66 (4) ◽  
pp. 316 ◽  
Author(s):  
Lavanya Raman ◽  
Karthick Gothandapani ◽  
B.S. Murty

Materials play an important role in the fast breeder reactors.  Materials used in cladding tube and fuel pins should have better creep and void swelling resistance. To overcome these difficulties, a new class of material known as oxide dispersion strengthened (ODS) steels are used. There are two groups of ODS steels, the ferritic and the austenitic ODS steels based on the matrix. The present paper reviews the current status of research in austenitic ODS steels. The interaction of dislocations with finely dispersed incoherent, hard particles that governs the strength and high temperature properties of ODS materials is briefly reviewed. The synthesis route adopted for these ODS steels, which is mostly through powder metallurgy route is also discussed. The role of various oxides such as Y2O3, ZrO2and TiO2and the clusters formed in these ODS steels on the mechanical properties and void swelling characteristics is also discussed.


2010 ◽  
Vol 638-642 ◽  
pp. 2309-2314
Author(s):  
Kei Shinozuka ◽  
Hisao Esaka ◽  
M. Tamura ◽  
Hiroyasu Tanigawa

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.


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