Development of accident tolerant FeCrAl-ODS steels utilizing Ce-oxide particles dispersion
Source abstract
Abstract
Abstract FeCrAl-ODS ferritic steels with Ce-oxide dispersion instead of Y-oxide were produced for the accident tolerant fuel cladding of the light water reactor. Excess oxygen (Ex.O) was added to improve the mechanical property. The tensile strength at Ex.O = 0 is around 200 MPa at 700 °C, mainly owing to dispersed Ce2O3 particles in less than 10 nm size. The formation of the fine Ce2O3 particles is dominated by a coherent interface with ferritic matrix. With increasing Ex.O, an increased of number density of coarser Ce-Al type oxide particles over 10 nm size is responsible for the improvement of the tensile strength. Change of the type of oxide particle, CeO2, Ce2O3, CeAlO3, Al2O3, in FeCrAl-ODS steel was thermodynamically analyzed as a parameter of Ex.O.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · High-Temperature Coating Behaviors
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (21)
Show source-provided references
1. Preliminary assessment of the possible BWR core/vessel damage states for Fukushima Daiichi station blackout scenarios using RELAP/SCDAPSIM10.1155/2012/646327 ↗
2. Advanced oxidation-resistant iron-based alloys for LWR fuel cladding10.1016/j.jnucmat.2013.06.041 ↗
3. Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors10.1016/j.anucene.2014.09.005 ↗
4. Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems10.1016/j.jnucmat.2010.12.300 ↗
5. Characterization of the oxide particles in Al-added high-Cr ODS ferritic steels10.1016/j.jnucmat.2010.12.063 ↗
6. Formation mechanism and the role of nanoparticles in Fe-Cr ODS steels developed for radiation tolerance10.1103/PhysRevB.82.184103 ↗
7. Y. Shizukawa, S. Ukai, N. Oono, S. Hayashi, S. Ohtsuka, T. Torimaru, A. Kimura, The effect of excess oxygen on the high temperature oxidation in Zr added FeCrAl ODS steel, Proc. on Advanced High-Temperature Materials Technology for Sustainable and Reliable Power Engineering (123HiMST-2015) 29 June-3 July (2015) Sapporo, Japan.
8. Development of FeCrAl-ODS steels for ATF cladding
9. Development of FeCrAl-ODS steels for accident tolerant fuel (ATF) cladding in light water reactors
10. S. Ukai, N. Oono, K. Sakamoto, T. Torimaru, T. Kaito, A. Kimura, S. Hayashi, Development of FeCrAl-ODS steels claddings for accident tolerant fuel of light water reactors, Proc. of ICAPP 2017, Fukui and Kyoto (Japan), April 24–28 (2017).
11. Phase diagram of the system Al2O3-CeO2 at liquids temperature10.2109/jcersj1950.83.954_90 ↗
12. Okamoto · 2014
13. New thermodynamic equilibrium calculation software10.1016/j.calphad.2008.09.015 ↗
14. Interfacial strained structure and orientation relationships of the nanosized oxide particles deduced from elasticity-driven morphology in oxide dispersion strengthened materials10.1016/j.actamat.2011.09.042 ↗
15. Coupled thermodynamic-phase diagram assessment of the rare earth oxid-aluminium oxide binary systems10.1016/0925-8388(92)90227-Z ↗
16. The Orowan mechanism in anisotropic crystals10.1080/14786437508229295 ↗
17. Oxide particle-dislocation interaction in 9Cr-ODS steel10.1016/j.nme.2016.06.014 ↗
18. Characterization of high temperature creep properties in recrystallized 12Cr-ODS ferritic steel cladding10.1080/18811248.2002.9715271 ↗
19. K. Sakamoto et al., Overview of Japanese Development of Accident Tolerant FeCrAl-ODS Fuel Cladding for BWRS, 2017 Water Reactor Fuel Performance Meeting.
20. On diffraction contrast from inclusions10.1080/14786436308207329 ↗
21. NIMS AtomWork Database · Phys. Status Solidi A · 1974 · 597