Since the nuclear accident at Fukushima Daiichi Nuclear Power Station in 2011, a considerable number of studies have been conducted to develop accident tolerant fuel (ATF) claddings for safety enhancement of light water reactors. Among many potential ATF claddings, silicon carbide is one of the most promising candidates with many superior features suitable for nuclear applications. In spite of many potential benefits of SiC cladding, there are some concerns over the oxidation/corrosion resistance of the cladding, especially at extreme temperatures (up to 2000 °C) in severe accidents. However, the study of SiC steam oxidation in conventional test facilities in water vapor atmospheres at temperatures above 1600 °C is very challenging. In...
Since the Fukushima disaster, efforts are made worldwide to improve the accident performance of nucl...
International audienceThe cladding material envisaged for the Gas-cooled Fast Reactor (GFR) is a SiC...
SiC has been under investigation as a potential cladding for LWR fuel, due to its high melting point...
Single-rod oxidation and quench experiments at very high temperatures in steam atmosphere were condu...
The commercial nuclear power industry is continually looking for ways to improve reactor productivit...
Three oxidation experiments at very high temperatures in steam atmosphere were conducted with advanc...
The chemical and mechanical aspects related to the use of refractory materials at high-temperatures ...
International audienceFive oxidation experiments at very high temperatures in steam atmosphere were ...
International audienceFive oxidation experiments at very high temperatures in steam atmosphere were ...
The inherent weakness of zirconium (Zr) based nuclear fuel cladding has been shown when performing o...
International audienceSingle-rod oxidation and quench experiments at very high temperatures in steam...
International audienceThree oxidation experiments at very high temperatures in steam atmosphere were...
International audienceThree oxidation experiments at very high temperatures in steam atmosphere were...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
One of the inherently safe technologies currently under development is a system to prevent hydrogen ...
Since the Fukushima disaster, efforts are made worldwide to improve the accident performance of nucl...
International audienceThe cladding material envisaged for the Gas-cooled Fast Reactor (GFR) is a SiC...
SiC has been under investigation as a potential cladding for LWR fuel, due to its high melting point...
Single-rod oxidation and quench experiments at very high temperatures in steam atmosphere were condu...
The commercial nuclear power industry is continually looking for ways to improve reactor productivit...
Three oxidation experiments at very high temperatures in steam atmosphere were conducted with advanc...
The chemical and mechanical aspects related to the use of refractory materials at high-temperatures ...
International audienceFive oxidation experiments at very high temperatures in steam atmosphere were ...
International audienceFive oxidation experiments at very high temperatures in steam atmosphere were ...
The inherent weakness of zirconium (Zr) based nuclear fuel cladding has been shown when performing o...
International audienceSingle-rod oxidation and quench experiments at very high temperatures in steam...
International audienceThree oxidation experiments at very high temperatures in steam atmosphere were...
International audienceThree oxidation experiments at very high temperatures in steam atmosphere were...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
One of the inherently safe technologies currently under development is a system to prevent hydrogen ...
Since the Fukushima disaster, efforts are made worldwide to improve the accident performance of nucl...
International audienceThe cladding material envisaged for the Gas-cooled Fast Reactor (GFR) is a SiC...
SiC has been under investigation as a potential cladding for LWR fuel, due to its high melting point...