Silicon dissolution and morphology modification of NITE SiC/SiC claddings in pressurized flowing water under neutron irradiation
Published 2021 View Full Article
- Home
- Publications
- Publication Search
- Publication Details
Title
Silicon dissolution and morphology modification of NITE SiC/SiC claddings in pressurized flowing water under neutron irradiation
Authors
Keywords
NITE SiC/SiC cladding, Accident tolerant fuel, Neutron irradiation, Water chemistry, Silicon dissolution
Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 557, Issue -, Pages 153253
Publisher
Elsevier BV
Online
2021-08-18
DOI
10.1016/j.jnucmat.2021.153253
References
Ask authors/readers for more resources
Related references
Note: Only part of the references are listed.- Hydrothermal corrosion of laser printed SiC fibers under extreme environment
- (2021) Arunkumar Seshadri et al. JOURNAL OF NUCLEAR MATERIALS
- Impact of nuclear environment on hydrothermal corrosion and silica transport for CVD SiC in light water reactors
- (2021) Arunkumar Seshadri et al. JOURNAL OF NUCLEAR MATERIALS
- Hydrothermal corrosion behavior of CVD SiC in high temperature water
- (2020) Peter J. Doyle et al. JOURNAL OF NUCLEAR MATERIALS
- Implications of SiC irradiation creep and annealing to UN-SiC fuel rod behavior
- (2020) Wei Li et al. JOURNAL OF NUCLEAR MATERIALS
- Hydrothermal Corrosion of First-Generation Dual-Purpose Coatings on Silicon Carbide for Accident-Tolerant Fuel Cladding
- (2020) Peter J. Doyle et al. JOURNAL OF NUCLEAR MATERIALS
- Factors affecting the hydrothermal corrosion behavior of chemically vapor deposited silicon carbides
- (2019) Jung Ho Shin et al. JOURNAL OF NUCLEAR MATERIALS
- Progress in development of SiC-based joints resistant to neutron irradiation
- (2019) Takaaki Koyanagi et al. JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
- Silicon carbide and its composites for nuclear applications – Historical overview
- (2019) Yutai Katoh et al. JOURNAL OF NUCLEAR MATERIALS
- Oxidation resistance of NITE-SiC/SiC composites with/without CVD-SiC environmental barrier coating
- (2018) Joon-Soo Park et al. CERAMICS INTERNATIONAL
- Appropriate thickness of pyrolytic carbon coating on SiC fiber reinforcement to secure reasonable quasi-ductility on NITE SiC/SiC composites
- (2018) Naofumi Nakazato et al. CERAMICS INTERNATIONAL
- CaO-Al 2 O 3 glass-ceramic as a joining material for SiC based components: A microstructural study of the effect of Si-ion irradiation
- (2018) Valentina Casalegno et al. JOURNAL OF NUCLEAR MATERIALS
- Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond
- (2018) Takashi Nozawa et al. JOURNAL OF NUCLEAR MATERIALS
- Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response
- (2018) Yangbin Deng et al. JOURNAL OF NUCLEAR MATERIALS
- Irradiation stability and thermo-mechanical properties of NITE-SiC irradiated to 10 dpa
- (2018) Kurt A. Terrani et al. JOURNAL OF NUCLEAR MATERIALS
- Specimen size effects on fracture behaviour of SiC/SiC tubes during circumferential tensile test
- (2018) Ju-Hyeon Yu et al. ADVANCED COMPOSITE MATERIALS
- Deformation analysis of SiC-SiC channel box for BWR applications
- (2018) G. Singh et al. JOURNAL OF NUCLEAR MATERIALS
- High speed formation of pyro-carbon coat on silicon carbide fiber by continuous chemical vapor deposition furnace
- (2017) Joon-Soo Park et al. FUSION ENGINEERING AND DESIGN
- Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux
- (2017) Christian M. Petrie et al. JOURNAL OF NUCLEAR MATERIALS
- Modification of MELCOR for severe accident analysis of candidate accident tolerant cladding materials
- (2017) Brad J. Merrill et al. NUCLEAR ENGINEERING AND DESIGN
- Gas leak tightness of SiC/SiC composites at elevated temperature
- (2016) Daisuke Hayasaka et al. FUSION ENGINEERING AND DESIGN
- Fabrication of short SiC fiber reinforced SiC matrix composites with high fiber volume fraction
- (2016) Joon-Soo Park et al. FUSION ENGINEERING AND DESIGN
- Circumferential tensile test method for mechanical property evaluation of SiC/SiC tube
- (2016) Ju-Hyeon Yu et al. FUSION ENGINEERING AND DESIGN
- Helium permeability of high-performance SiC/SiC tube
- (2016) Daisuke Hayasaka et al. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
- Effect of dissolved hydrogen on the corrosion behavior of chemically vapor deposited SiC in a simulated pressurized water reactor environment
- (2015) Daejong Kim et al. CORROSION SCIENCE
- Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation
- (2015) K.A. Terrani et al. JOURNAL OF NUCLEAR MATERIALS
- Characterization of SiC–SiC composites for accident tolerant fuel cladding
- (2015) C.P. Deck et al. JOURNAL OF NUCLEAR MATERIALS
- Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding
- (2015) J.G. Stone et al. JOURNAL OF NUCLEAR MATERIALS
- Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear application
- (2015) V. Angelici Avincola et al. NUCLEAR ENGINEERING AND DESIGN
- Current status and recent research achievements in SiC/SiC composites
- (2014) Y. Katoh et al. JOURNAL OF NUCLEAR MATERIALS
- Silicon Carbide Oxidation in Steam up to 2 MPa
- (2014) Kurt A. Terrani et al. JOURNAL OF THE AMERICAN CERAMIC SOCIETY
- Galvanic corrosion of metal/ceramic coupling
- (2013) M. Schneider et al. CORROSION SCIENCE
- Long-term corrosion behavior of CVD SiC in 360°C water and 400°C steam
- (2013) Jeong-Yong Park et al. JOURNAL OF NUCLEAR MATERIALS
- High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
- (2013) B.A. Pint et al. JOURNAL OF NUCLEAR MATERIALS
- Accident tolerant fuels for LWRs: A perspective
- (2013) S.J. Zinkle et al. JOURNAL OF NUCLEAR MATERIALS
- Silicon Carbide Oxidation in High-Pressure Steam
- (2013) Ting Cheng et al. JOURNAL OF THE AMERICAN CERAMIC SOCIETY
- SiC/SiC composite heater for IFMIF
- (2012) T. Abe et al. FUSION ENGINEERING AND DESIGN
- The role of Pd in the transport of Ag in SiC
- (2012) E.J. Olivier et al. JOURNAL OF NUCLEAR MATERIALS
- Microstructure and mechanical properties of joints in sintered SiC fiber-bonded ceramics brazed with Ag–Cu–Ti alloy
- (2012) Mrityunjay Singh et al. MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
- Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures
- (2010) Yutai Katoh et al. JOURNAL OF NUCLEAR MATERIALS
- Low-activation joining of SiC/SiC composites for fusion applications
- (2010) Charles H. Henager et al. JOURNAL OF NUCLEAR MATERIALS
- Advanced SiC fibers and SiC/SiC composites toward industrialization
- (2010) Akira Kohyama et al. JOURNAL OF NUCLEAR MATERIALS
- Thermal stress relaxation creep and microstructural evolutions of nanostructured SiC ceramics by liquid phase sintering
- (2010) Kazuya Shimoda et al. JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
- R&D of joining technology for SiC components with channel
- (2009) Hun-Chea Jung et al. JOURNAL OF NUCLEAR MATERIALS
- Development of advanced blanket performance under irradiation and system integration through JUPITER-II project
- (2008) K. Abe et al. FUSION ENGINEERING AND DESIGN
- Microstructures of beta-silicon carbide after irradiation creep deformation at elevated temperatures
- (2008) Yutai Katoh et al. JOURNAL OF NUCLEAR MATERIALS
- Microstructural defects in SiC neutron irradiated at very high temperatures
- (2008) S. Kondo et al. JOURNAL OF NUCLEAR MATERIALS
- Cavity swelling and dislocation evolution in SiC at very high temperatures
- (2008) S. Kondo et al. JOURNAL OF NUCLEAR MATERIALS
Find Funding. Review Successful Grants.
Explore over 25,000 new funding opportunities and over 6,000,000 successful grants.
ExploreDiscover Peeref hubs
Discuss science. Find collaborators. Network.
Join a conversation