Zirconium based alloys are commonly used as material for fuel claddings in the light water reactors. Claddings act as first metallic barriers against loss of fission products during the nuclear power plant operation, intermittent storage or final dry storage. The integrity of claddings is always critical issue during reactor operation and during storage of spent fuel. In this work, ring compression testing method developed was applied to study hydrogen embrittlement, to evaluate the stressstrain behaviour and hoop fracture properties of E110 (Zr-based) fuel claddings. The results show that the collapse load and the tensile strength values depend strongly on hydrogen concentration. In particular, tensile strength experiment data shows signif...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized b...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
In this work, a new methodology is devised to obtain the fracture properties of nuclear fuel claddin...
The presented data is the raw data of ring compression tests on un-irradiated Zircaloy-4 PWR fuel cl...
Spent nuclear fuel claddings discharged from water reactors contain hydrogen up to 800 wppm dependin...
When Zirconium claddings are exposed to irradiation and oxidation in reactor, after a certain period...
Hydrogen content is a very important parameter for mechanical properties of fuel cladding, especiall...
Zirconium alloys are being commonly used as a material of choice for nuclear fuel claddings in water...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized b...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
In this work, a new methodology is devised to obtain the fracture properties of nuclear fuel claddin...
The presented data is the raw data of ring compression tests on un-irradiated Zircaloy-4 PWR fuel cl...
Spent nuclear fuel claddings discharged from water reactors contain hydrogen up to 800 wppm dependin...
When Zirconium claddings are exposed to irradiation and oxidation in reactor, after a certain period...
Hydrogen content is a very important parameter for mechanical properties of fuel cladding, especiall...
Zirconium alloys are being commonly used as a material of choice for nuclear fuel claddings in water...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized b...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...