Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions

Yano, Yasuhide; Tanno, Takashi; Oka, Hiroshi; Ohtsuka, Satoshi; Inoue, Toshihiko; Kato, Shoichi; Furukawa, Tomohiro; Uwaba, Tomoyuki; Kaito, Takeji; Ukai, Shigeharu; Oono, Naoko; Kimura, Akihiko; Hayashi, Shigenari; Torimaru, Tadahiko

doi:10.1016/j.jnucmat.2017.02.021

Cited by 47 publications

(10 citation statements)

References 18 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…and fully ceramic micro-encapsulated fuels 5 . The potential claddings mainly include coated zirconium alloy [6][7][8][9] , refractory metal 10 , advanced steels [11][12][13] , and SiC f / SiC [14][15][16] claddings. Among the ATF candidate materials, complete replacements of current Zr alloy with refractory metal, advanced steels or SiC f /SiC imply a substantial evolution from the current LWR system, indicative of great difficulties and uncertainties.…”

Section: Introductionmentioning

confidence: 99%

Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200 °C

et al. 2021

View full text Add to dashboard Cite

Dense, uniform, and well-adhered chromium (Cr) coatings were deposited on zirconium (Zr) alloy claddings by using physical vapor deposition (PVD). The Cr-coated samples were tested at 1200 oC and 1300 oC, respectively, for different exposure time in water steam environment. Microstructures and compositions of the coating/substrate system after oxidation were characterized by X-ray diffraction, scanning electronic microscopy, and energy dispersion spectrometer. The microstructural results clearly demonstrated that Cr2O3 layer has been produced on the coating surface, acting as an oxygen diffusion barrier and concomitantly reducing the oxidation rate. The experimental results on weight gains soundly supported the microstructural findings that the Cr coatings could protect the Zr substrate from high-temperature steam oxidation, even at a temperature up to 1300 oC. Finally, the oxidation kinetics was theoretically analyzed and the underlying oxidation mechanism was also clarified.

show abstract

Section: Introductionmentioning

confidence: 99%

Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200 °C

et al. 2021

View full text Add to dashboard Cite

show abstract

“…For Z7, it was of interest to see whether higher ductility could be accomplished through full recrystallization followed by some additional deformation. Fully recrystallized ODS FeCrAl alloys were recently demonstrated to have at least some ductility and attractive high-temperature strength [17,18]. However, full recrystallization reduces the yield and ultimate tensile strength appreciably due to the loss of essentially all Hall-Petch strengthening; thus, it was of interest in this work to see whether additional dislocations could be reintroduced into the microstructure via cold work to increase the dislocation strengthening of the microstructure since the dislocations would be easily pinned by existing oxide precipitates.…”

Section: μMmentioning

confidence: 99%

STEP Report on Advanced ODS FeCrAl Alloys for Fission Applications

Massey¹,

Austin

Dryepondt³

et al. 2020

View full text Add to dashboard Cite

“…ODS steels also being used for improvement of zircaloy as the current cladding materials for LWR for a coating material in order to increase the high-temperature strength and corrosion-oxidation resistance is reported [3,4]. ODS steels are reported have high performance of mechanic characteristics at elevated temperature [5,6]. Related to ATF cladding development, FeCrAl alloy is one of the most promising candidates because of its excellent high-temperature oxidation resistance, corrosion resistance and high-temperature mechanical properties [7][8][9][10].…”

Section: Introductionmentioning

confidence: 99%

Microstructure Investigation of Mechanically Alloyed 316L-6Al-0.5Y₂O₃ Oxide Dispersion Strengthened Austenitic Steel Powder

Rivai

Pratama²,

Sugeng

2022

J. Phys.: Conf. Ser.

View full text Add to dashboard Cite

Development of accident-tolerant fuel cladding (ATFC) materials for LWRs (Light Water Reactors) is being intensively carried out in many research centers in the world as the lesson-learned from the Fukushima Daiichi nuclear reactor power plant accident. One of the advanced high temperature materials which is intensively developed is Oxide Dispersion Strengthened (ODS) steel. The strengthened mechanism is generated by homogeneous dispersion of nano-meter sized ceramic oxide particles in the matrix of the steel which is done by mechanical alloying technique so called mechanosynthesis. Synthesis of an austenitic ODS steel powder of 316L with additional element of 6 wt.% aluminum and dispersion of nano-particles of 0.5 wt.% yttrium oxide (yttria: Y2O3) has been done. The aim of the research is to achieve a better performance of 316L austenitic steel as the proven material for power plant at elevated temperature by modified to become ODS austenitic steel with additional of aluminum. Mechanosynthesis was done using High Energy ball Milling (HEM) for 30 hours with BPR (Ball to Powder Ratio) of 10:1. Afterward, the sample was characterized using Scanning Electron Microscope-Energy Dispersive Spectroscope (SEM-EDS) and X-ray Diffraction (XRD) to analyze the microstructure characteristics. The results showed that the alloying between 316L and aluminum powders was formed. Furthermore, crystal grains and the particles of 316L-6Al-0.5Y2O3 steel powder was much smaller than as received 316L austenitic steel and aluminium powders. The particles size and element composition was homogeneously distributed. The results showed that the parameters of mechanical alloying for development of 316L-6Al-0.5Y2O3 ODS austenitic steel powder have reached the optimum condition.

show abstract

Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions

Cited by 47 publications

References 18 publications

Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200 °C

Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200 °C

STEP Report on Advanced ODS FeCrAl Alloys for Fission Applications

Microstructure Investigation of Mechanically Alloyed 316L-6Al-0.5Y₂O₃ Oxide Dispersion Strengthened Austenitic Steel Powder

Contact Info

Product

Resources

About

Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions

Cited by 47 publications

References 18 publications

Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200 °C

Oxidation behavior of Cr-coated zirconium alloy cladding in high-temperature steam above 1200 °C

STEP Report on Advanced ODS FeCrAl Alloys for Fission Applications

Microstructure Investigation of Mechanically Alloyed 316L-6Al-0.5Y2O3 Oxide Dispersion Strengthened Austenitic Steel Powder

Contact Info

Product

Resources

About

Microstructure Investigation of Mechanically Alloyed 316L-6Al-0.5Y₂O₃ Oxide Dispersion Strengthened Austenitic Steel Powder