International audienceIn order to obtain experimental data on the complex corium pool involved during a severe accident in a nuclear reactor as a first approximation U-Zr-Fe-O experiments at very high temperatures have to be performed (T>2300 K). However, when samples are in direct contact with the instrumentation (e.g., thermocouples) or with a crucible, inevitable chemical interactions affect the experimental measurements. Furthermore, handling radioactive materials impose radioprotection restrictions.In this framework, a novel experimental setup called ATTILHA has been conceived and developed CEA Saclay. The setup has the final objective to study the high temperature thermodynamics and thermophysical properties of liquid nuclear materi...
International audienceDuring a severe accident in a pressurised water reactor, the nuclear fuel can ...
In the framework of improving nuclear power plant safety during accidents, the current study is focu...
International audienceUp to now, predicting accurately the Fission Gas Release (FGR) from high burn ...
International audienceIn order to obtain experimental data on the complex corium pool involved durin...
International audienceDuring a severe accident in a Pressurized or Boiling Water nuclear reactor, ex...
International audienceDuring a severe accident in a pressurised water reactor, the nuclear fuel can ...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
During a severe nuclear accident, the UO2 fuel rods, Zircaloy cladding, guide tubes, absorber and st...
International audienceDuring a severe accident in a nuclear reactor, the nuclear fuel (UO$_2$ or MOx...
International audienceDuring a severe accident in a PWR reactor, the oxide nuclear fuel (UO2 or MOX)...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
International audienceIn order to simulate, on a laboratory scale, the high-temperature interaction ...
International audienceDuring a severe accident in a pressurised water reactor, the nuclear fuel can ...
In the framework of improving nuclear power plant safety during accidents, the current study is focu...
International audienceUp to now, predicting accurately the Fission Gas Release (FGR) from high burn ...
International audienceIn order to obtain experimental data on the complex corium pool involved durin...
International audienceDuring a severe accident in a Pressurized or Boiling Water nuclear reactor, ex...
International audienceDuring a severe accident in a pressurised water reactor, the nuclear fuel can ...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
During a severe nuclear accident, the UO2 fuel rods, Zircaloy cladding, guide tubes, absorber and st...
International audienceDuring a severe accident in a nuclear reactor, the nuclear fuel (UO$_2$ or MOx...
International audienceDuring a severe accident in a PWR reactor, the oxide nuclear fuel (UO2 or MOX)...
International audienceDuring a severe accident in a nuclear reactor, extreme temperatures may be rea...
International audienceIn order to simulate, on a laboratory scale, the high-temperature interaction ...
International audienceDuring a severe accident in a pressurised water reactor, the nuclear fuel can ...
In the framework of improving nuclear power plant safety during accidents, the current study is focu...
International audienceUp to now, predicting accurately the Fission Gas Release (FGR) from high burn ...