Upcoming advanced nuclear power reactors contemplate partial boiling inside the core and it is important to establish the effects of partial boiling on oxidation and hydrogen pick up for sufficiently long periods of time. The effect of partial boiling on oxidation behaviour was assessed in this study in terms of change in the level of dissolved oxygen (DO) in static autoclaves. The results clearly demonstrated that the oxidation behaviour of Zircaloy-2 is quite immune to the level of dissolved oxygen, while Zr–Nb alloys showed very different oxidation behaviour with change in the dissolved oxygen level. The weight gain due to oxidation in Zr–Nb alloys during long term exposure was almost doubled with increase in the DO level. Nevertheless, ...
The electrochemical characteristics of a Zr-Nb-Sn zirconium alloy have been investigated at 360 degr...
International audienceDuring hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear ...
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...
This thesis was part of the MUZIC-2 collaboration and describes the effect of different water chemis...
Zirconium oxidation by water is accompanied by hydrogen conversion, either H2 is released or hydroge...
International audienceWhile Zircaloy-4 alloy shows a high and constant hydrogen pickup fraction over...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years ...
Hydrogen pick-up during corrosion of nuclear fuel cladding is a critical life-limiting degradation m...
The TREAT facility, located at the Idaho National Laboratory, is an air-cooled test facility designe...
Zirconium-based fuel cladding used in nuclear reactors is susceptible to significant hydrogen uptake...
When Zirconium claddings are exposed to irradiation and oxidation in reactor, after a certain period...
Zr cladding alloys have been used for many years as the first safety barrier layer of a nuclear reac...
A comprehensive first principles understanding of the oxidation of zirconium alloys by water was rei...
The evolution of Cr and Fe within the oxide formed on Zircaloy-4 in high-temperature pure water and ...
The electrochemical characteristics of a Zr-Nb-Sn zirconium alloy have been investigated at 360 degr...
International audienceDuring hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear ...
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...
This thesis was part of the MUZIC-2 collaboration and describes the effect of different water chemis...
Zirconium oxidation by water is accompanied by hydrogen conversion, either H2 is released or hydroge...
International audienceWhile Zircaloy-4 alloy shows a high and constant hydrogen pickup fraction over...
The oxidation of zirconium alloys under aqueous conditions has been studied for more than 50 years ...
Hydrogen pick-up during corrosion of nuclear fuel cladding is a critical life-limiting degradation m...
The TREAT facility, located at the Idaho National Laboratory, is an air-cooled test facility designe...
Zirconium-based fuel cladding used in nuclear reactors is susceptible to significant hydrogen uptake...
When Zirconium claddings are exposed to irradiation and oxidation in reactor, after a certain period...
Zr cladding alloys have been used for many years as the first safety barrier layer of a nuclear reac...
A comprehensive first principles understanding of the oxidation of zirconium alloys by water was rei...
The evolution of Cr and Fe within the oxide formed on Zircaloy-4 in high-temperature pure water and ...
The electrochemical characteristics of a Zr-Nb-Sn zirconium alloy have been investigated at 360 degr...
International audienceDuring hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear ...
The Transient Reactor Test (TREAT) facility at the Idaho National Laboratory currently utilizes a le...