Potential air ingress scenarios during accidents in nuclear reactors or spent fuel pools have raised the question of the influence of air, especially of nitrogen, on the oxidation of zirconium alloys, which are used as fuel cladding tubes and other structure materials. In this context, the reaction of zirconium with nitrogen-containing atmospheres and the formation of zirconium nitride play an important role in understanding the oxidation mechanism. This article presents the results of analysis of the interaction of the oxygen-preloaded niobium-bearing alloy M5® with nitrogen over a wide range of temperatures (800–1400°C) and oxygen contents in the metal alloy (1–7 wt.%). A strongly increasing nitriding rate with rising oxygen content in th...
Zircaloy-4 claddings provide the first containment of UO2 fuel in Pressurised Water Reactors. It has...
atmospheres This article is devoted to the qualitative analysis of the Zircaloy-4 degradation mechan...
In nuclear plants, some accidental situations can result in air exposure of Pressurized Water Reacto...
Potential air ingress scenarios during accidents in nuclear reactors or spent fuel pools have raised...
International audienceZirconium-based alloys used in PWR cladding show an acceleration of their oxid...
High temperature reactivity in air and in nitrogen of pre-oxidised Zircaloy-4 and M5™ claddings has ...
In the event of air ingress during a reactor or spent fuel pond low probability accident, the fuel r...
Zirconium alloys are routinely used as fuel cladding materials in nuclear reactors due to the low ab...
This study presents results of overall 124 oxidation tests of Zircaloy-4 at 900°C, 1000°C and 1100°C...
Zirconium metal was heated in nitrogen, oxygen, and air at temperatures ranging from 425 to 1300 C. ...
International audienceThis article is devoted to the qualitative analysis of the Zircaloy-4 degradat...
The TREAT facility, located at the Idaho National Laboratory, is an air-cooled test facility designe...
U3O8; kinetics; oxygen partial pressure; pseudo steady state; rate-limiting step. The oxidation by w...
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...
Zircaloy-4 claddings provide the first containment of UO2 fuel in Pressurised Water Reactors. It has...
atmospheres This article is devoted to the qualitative analysis of the Zircaloy-4 degradation mechan...
In nuclear plants, some accidental situations can result in air exposure of Pressurized Water Reacto...
Potential air ingress scenarios during accidents in nuclear reactors or spent fuel pools have raised...
International audienceZirconium-based alloys used in PWR cladding show an acceleration of their oxid...
High temperature reactivity in air and in nitrogen of pre-oxidised Zircaloy-4 and M5™ claddings has ...
In the event of air ingress during a reactor or spent fuel pond low probability accident, the fuel r...
Zirconium alloys are routinely used as fuel cladding materials in nuclear reactors due to the low ab...
This study presents results of overall 124 oxidation tests of Zircaloy-4 at 900°C, 1000°C and 1100°C...
Zirconium metal was heated in nitrogen, oxygen, and air at temperatures ranging from 425 to 1300 C. ...
International audienceThis article is devoted to the qualitative analysis of the Zircaloy-4 degradat...
The TREAT facility, located at the Idaho National Laboratory, is an air-cooled test facility designe...
U3O8; kinetics; oxygen partial pressure; pseudo steady state; rate-limiting step. The oxidation by w...
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...
Zircaloy-4 claddings provide the first containment of UO2 fuel in Pressurised Water Reactors. It has...
atmospheres This article is devoted to the qualitative analysis of the Zircaloy-4 degradation mechan...
In nuclear plants, some accidental situations can result in air exposure of Pressurized Water Reacto...