AbstractIn the framework of the post-test examinations of the large-scale LOCA simulation tests at the fuel rod bundle scale, the hydrogen distributions in specimens prepared from the QUENCH-L0 and -L1 tests were studied by means of neutron radiography and tomography. In order to determine quantitative hydrogen concentrations, both, neutron radiography and tomography were calibrated using cladding tube segments with known hydrogen concentrations. The linear dependence of the total macroscopic neutron cross section with the H/Zr atomic ratio was determined for both methods.The hydrogen distributions in samples prepared from the two tests differ significantly as a first glance to the results obtained for the QUENCH-L1 shows. Whereas clearly v...
International audienceHydrogen and oxygen are key elements influencing the embrittlement of zirconiu...
Hydrogen uptake by nuclear fuel claddings during normal operation as well as loss of coolant during ...
Zr-based alloys are used in nuclear power plants because of a unique combination of very low neutron...
AbstractIn the framework of the post-test examinations of the large-scale LOCA simulation tests at t...
The hydrogen concentration and distribution at both sides of the burst opening of cladding tubes use...
AbstractThe hydrogen concentration and distribution at both sides of the burst opening of cladding t...
AbstractHydrogen content and distribution in Zircaloy-4 cladding samples with controlled hydrogen co...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
In situ neutron radiography experiments can provide information about diffusive processes and the ki...
International audienceThis paper gives an overview of a multi-scale experimental study of the second...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
The presence of hydrogen (H) and zirconium hydrides (ZrH1.7) in Zircaloy-4 nuclear fuel cladding has...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceHydrogen and oxygen are key elements influencing the embrittlement of zirconiu...
Hydrogen uptake by nuclear fuel claddings during normal operation as well as loss of coolant during ...
Zr-based alloys are used in nuclear power plants because of a unique combination of very low neutron...
AbstractIn the framework of the post-test examinations of the large-scale LOCA simulation tests at t...
The hydrogen concentration and distribution at both sides of the burst opening of cladding tubes use...
AbstractThe hydrogen concentration and distribution at both sides of the burst opening of cladding t...
AbstractHydrogen content and distribution in Zircaloy-4 cladding samples with controlled hydrogen co...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
In situ neutron radiography experiments can provide information about diffusive processes and the ki...
International audienceThis paper gives an overview of a multi-scale experimental study of the second...
The QUENCH-LOCA project on out-of-pile bundle tests under conditions of a loss of coolant reactor ac...
The presence of hydrogen (H) and zirconium hydrides (ZrH1.7) in Zircaloy-4 nuclear fuel cladding has...
International audienceDuring oxidization in steam at High Temperature (HT) under hypothetical Loss-O...
International audienceHydrogen and oxygen are key elements influencing the embrittlement of zirconiu...
Hydrogen uptake by nuclear fuel claddings during normal operation as well as loss of coolant during ...
Zr-based alloys are used in nuclear power plants because of a unique combination of very low neutron...