The quenching of LWR cladding is investigated in order to understand the behaviour of a LWR core during the injection of water in the course of a possible accident. A series of single tube tests is conducted in order to establish a data base providing information about the phenomena: oxide layer formation, cracking and hydrogen generation. Oxide layer formation and cracking after the experiments may be documented with a microscope and an image processing system. The hardware, the preparation methods and the software of this tube surface documentation system are described in the report. A number of tube surfaces have been examined. The class of penetrating cracks was found to be correlated with the oxide layer thickness. The density of these...
The integrity of structures exhibiting flaws in Pressurized Water Reactor (PWR) has to be assessed t...
BS>A Zircaloy-clad tube of unalloyed uranium that was irradiated in a loop of the NRU reactor to a m...
During hypothetical Loss-Of-Coolant-Accident (LOCA) scenarios, zirconium alloy fuel cladding tubes a...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...
In all severe accidents scenarios the main goal of operator actions (AMM, accident management measur...
International audienceDuring reactivity initiated accident, the importance of cladding tube oxidatio...
International audienceIn the frame of its research work on nuclear fuel safety, the French “Institut...
Zirconium alloys have been used as fuel cladding and structural fuel assembly components in nuclear ...
International audienceThe integrity of structures exhibiting flaws in Pressurized Water Reactor (PWR...
International audienceZirconium alloys are typically used in nuclear pressurized water reactors (PWR...
International audienceThis work addressed fracture mechanisms of nuclear fuel claddings in hypotheti...
A series of separate-effects tests is being carried out on Zircaloy PWR fuel rod cladding to study t...
Twenty-one LWBR irradiation test rods containing ThO/sub 2/-UO/sub 2/ fuel and Zircaloy cladding wit...
International audienceThe aim of this work is to study strain and fracture mechanisms of zircaloy 4 ...
The failure of defected Zircaloy-2-clad uranium and uranium -2 wt.% zircorium fuel specimens in high...
The integrity of structures exhibiting flaws in Pressurized Water Reactor (PWR) has to be assessed t...
BS>A Zircaloy-clad tube of unalloyed uranium that was irradiated in a loop of the NRU reactor to a m...
During hypothetical Loss-Of-Coolant-Accident (LOCA) scenarios, zirconium alloy fuel cladding tubes a...
International audienceThis paper investigates the room temperature cladding embrittlement of Stress ...
In all severe accidents scenarios the main goal of operator actions (AMM, accident management measur...
International audienceDuring reactivity initiated accident, the importance of cladding tube oxidatio...
International audienceIn the frame of its research work on nuclear fuel safety, the French “Institut...
Zirconium alloys have been used as fuel cladding and structural fuel assembly components in nuclear ...
International audienceThe integrity of structures exhibiting flaws in Pressurized Water Reactor (PWR...
International audienceZirconium alloys are typically used in nuclear pressurized water reactors (PWR...
International audienceThis work addressed fracture mechanisms of nuclear fuel claddings in hypotheti...
A series of separate-effects tests is being carried out on Zircaloy PWR fuel rod cladding to study t...
Twenty-one LWBR irradiation test rods containing ThO/sub 2/-UO/sub 2/ fuel and Zircaloy cladding wit...
International audienceThe aim of this work is to study strain and fracture mechanisms of zircaloy 4 ...
The failure of defected Zircaloy-2-clad uranium and uranium -2 wt.% zircorium fuel specimens in high...
The integrity of structures exhibiting flaws in Pressurized Water Reactor (PWR) has to be assessed t...
BS>A Zircaloy-clad tube of unalloyed uranium that was irradiated in a loop of the NRU reactor to a m...
During hypothetical Loss-Of-Coolant-Accident (LOCA) scenarios, zirconium alloy fuel cladding tubes a...