scholarly journals Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications

2016 ◽  
Vol 48 (2) ◽  
pp. 572-594 ◽  
Author(s):  
Tae Kyu Kim ◽  
Sanghoon Noh ◽  
Suk Hoon Kang ◽  
Jin Ju Park ◽  
Hyun Ju Jin ◽  
...  
2018 ◽  
Vol 119 (13) ◽  
pp. 1350-1353
Author(s):  
V. V. Sagaradze ◽  
K. A. Kozlov ◽  
N. V. Kataeva

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.


Atomic Energy ◽  
2014 ◽  
Vol 116 (1) ◽  
pp. 42-47 ◽  
Author(s):  
I. I. Chernov ◽  
M. S. Stal’tsov ◽  
B. A. Kalin ◽  
I. A. Bogachev ◽  
M. A. Burlakova ◽  
...  

2015 ◽  
Vol 89 ◽  
pp. 141-152 ◽  
Author(s):  
Xiaodong Mao ◽  
Kyu Hwan Oh ◽  
Suk Hoon Kang ◽  
Tae Kyu Kim ◽  
Jinsung Jang

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