Zirconium (Zr) alloys are used as nuclear fuel cladding in water-cooled nuclear reactors. Being in contact with steam, the Zr-alloy is oxidised and it absorbs hydrogen. The hydrogen pickup in Zr-alloys induces embrittlement of the tubes due to hydride formation. In this study, effectiveness of corrosion resistant nanocrystalline titanium zirconium nitride (nc-TiZrN) coatings on the surface of a Zr-alloy for the reduction of corrosion and hydrogen pickup is investigated. The nc-TiZrN layers were deposited onto the surface of ZIRLO® using the cathodic arc vapour deposition (CAVD) technique. The influence of nc-TiZrN coatings on the corrosion performance of ZIRLO® was investigated under the following conditions: (a) In an oxygen atmosphere at ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
In March 2011, the Fukushima Daiichi Nuclear Disaster changed the course of nuclear power production...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
Zirconium (Zr) alloys are used as nuclear fuel cladding in water-cooled nuclear reactors. Being in c...
Zirconium (Zr) alloys are used as fuel cladding material in all modern water cooled commercial nucle...
Zirconium (Zr) alloys are used as fuel cladding material in all modern water cooled commercial nucle...
Zirconium-based alloys are currently used as fuel rod cladding in nuclear power reactors because of ...
In this work, we demonstrate and describe an effective method of protecting zirconium fuel cladding ...
In March 2011, the Fukushima Daiichi Nuclear Disaster changed the course of nuclear power production...
The accident tolerant fuel (ATF) concept has emerged in the years after the 2011 Fukushima accident ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
Worldwide, zirconium alloys have long been utilised for fuel cladding elements and other structural ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
In March 2011, the Fukushima Daiichi Nuclear Disaster changed the course of nuclear power production...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
Zirconium (Zr) alloys are used as nuclear fuel cladding in water-cooled nuclear reactors. Being in c...
Zirconium (Zr) alloys are used as fuel cladding material in all modern water cooled commercial nucle...
Zirconium (Zr) alloys are used as fuel cladding material in all modern water cooled commercial nucle...
Zirconium-based alloys are currently used as fuel rod cladding in nuclear power reactors because of ...
In this work, we demonstrate and describe an effective method of protecting zirconium fuel cladding ...
In March 2011, the Fukushima Daiichi Nuclear Disaster changed the course of nuclear power production...
The accident tolerant fuel (ATF) concept has emerged in the years after the 2011 Fukushima accident ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
Worldwide, zirconium alloys have long been utilised for fuel cladding elements and other structural ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...
In March 2011, the Fukushima Daiichi Nuclear Disaster changed the course of nuclear power production...
The oxidation behaviours of ZrN, TiN and TiSiN in a steam environment in the high temperature range ...