2017
DOI: 10.1007/978-3-319-68454-3_22
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Hydrothermal Corrosion of SiC Materials for Accident Tolerant Fuel Cladding with and Without Mitigation Coatings

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Cited by 5 publications
(5 citation statements)
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“…Due to its high melting point and excellent mechanical and thermal properties, SiC can be applied in energy, aerospace, and nuclear industries [7]. SiC is a candidate material for the coating of TRISO nuclear fuel and for the Accident Tolerant Fuel Cladding (ATFC) in Pressurized Water-cooled Reactor (PWR) to enhance the inherent safety system so that the nuclear accident such as Fukushima Daiichi accident in 2011 will not be happened anymore in the future [8][9][10][11][12].…”
Section: Introductionmentioning
confidence: 99%
“…Due to its high melting point and excellent mechanical and thermal properties, SiC can be applied in energy, aerospace, and nuclear industries [7]. SiC is a candidate material for the coating of TRISO nuclear fuel and for the Accident Tolerant Fuel Cladding (ATFC) in Pressurized Water-cooled Reactor (PWR) to enhance the inherent safety system so that the nuclear accident such as Fukushima Daiichi accident in 2011 will not be happened anymore in the future [8][9][10][11][12].…”
Section: Introductionmentioning
confidence: 99%
“…Corrosion-resistant coatings processed using industrial technologies, such as physical vapor deposition (PVD), CVD, electrolytic deposition, and vacuum plasma spraying (VPS) have been researched [37][38][39][40][41][42][43][44][45][46][47][48][49][50][51]. Metals (such as Cr [37][38][39][40][41][42][43][44][45][46][47][48][49], Zr [37,47] and Ti [47][48][49][50]), metal-doped SiC (such as Ti-doped and Zr-doped SiC [51]) and metal nitrides (such as CrN [37][38][39][40][41][42][43], ZrN [39,40], and TiN [37,[39][40][41][42]…”
Section: Introductionmentioning
confidence: 99%
“…Preliminary work included the deposition of Cr, Zr, CrN, TiN, and ZrN coatings on SiC by PVD and VPS [36][37][38][39]. Hydrothermal corrosion testing for 1.4 × 10 6 s (400 h) without irradiation showed that Cr, CrN, and TiN coatings on SiC by PVD remained in simulated BWR-NWC environment [39,40]. Cr, CrN and TiN coatings on SiC indicated large mass loss at test durations between 2.2 × 10 6 s (600 h) and 4.0 × 10 6 s (1100 h) in simulated BWR-NWC environment, while they indicated small mass change for 4.0 × 10 6 s (1100 h) in simulated BWR-hydrogen water chemistry (HWC) environment and for 1.8 × 10 6 s (500 h) in simulated PWR environment [41].…”
Section: Introductionmentioning
confidence: 99%
“…They have previously compared the hydrothermal corrosion resistance of CVD SiC samples with different coatings, all of which were exposed in an autoclave of 288°C water for 400 hours. The Cr coating exhibited the least amount of mass change [ 6 ]. Some initial tests show favorable corrosion resistance of the Cr-based coatings.…”
Section: Introductionmentioning
confidence: 99%
“…Since the nuclear accident in Japan in 2011, considerable research has been devoted to the development of accident tolerant fuel (ATF) cladding for light-water reactors (LWRs). Nowadays, SiC/SiC f ceramic matrix composites are considered as a potential material for nuclear fuel claddings in USA, Korea, France, and Japan [1][2][3][4][5][6][7][8][9][10][11]. The silicon carbide (SiC) exhibits excellent oxidation resistance under the accident conditions such as in a typical loss of coolant accident (LOCA) scenario [12][13][14][15][16], where a protective SiO 2 layer can form on the surfaces in the >1000 °C steam, preventing breakaway oxidation [17].…”
Section: Introductionmentioning
confidence: 99%