This paper presents simulations of the VERDON 1 and RT6 tests (temperature increase up to fuel-clad melting, oxidizing and/or reducing conditions within the furnace) performed with high burnup UO 2 fuel (i.e., up to 72 GWd/tU) and considering a coupling between irradiated fuel thermochemistry and a fission gas release model. The thermochemical calculations rely on the Thermodynamics of Advanced Fuels-International Database (TAF-ID) for the description of the phases likely to form from the 15 fission product considered in the fuel (Ba
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
Abstract –Fuel irradiation testing and post-irradiation examination are currently in progress as par...
During a hypothetical severe nuclear accident involving a pressurised water reactor, it is of primar...
This paper presents simulations of the VERDON 1 and RT6 tests (temperature increase up to fuel-clad ...
This paper presents simulations of four tests performed on medium to high burnup fuel during the VER...
In this paper, a novel approach where irradiated fuel thermochemistry and gas release are coupled is...
In the first part of the paper, experimental results for the Xe depletion in the matrix of high burn...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
International audienceWithin the framework of the International Source Term Programme (ISTP), the VE...
International audienceThe capabilities of the Thermodynamic of Advanced Fuels – International Databa...
International audienceWithin the PLEIADES simulation platform co-developed by CEA, EDF and FRAMATOME...
International audienceThis paper describes the first VERDON test performed at the end of September 2...
Various countries engaged in the development and fabrication of modern HTGR fuel have initiated acti...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
International audienceIn this work, two different thermodynamic softwares, ANGE using the TBASE data...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
Abstract –Fuel irradiation testing and post-irradiation examination are currently in progress as par...
During a hypothetical severe nuclear accident involving a pressurised water reactor, it is of primar...
This paper presents simulations of the VERDON 1 and RT6 tests (temperature increase up to fuel-clad ...
This paper presents simulations of four tests performed on medium to high burnup fuel during the VER...
In this paper, a novel approach where irradiated fuel thermochemistry and gas release are coupled is...
In the first part of the paper, experimental results for the Xe depletion in the matrix of high burn...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
International audienceWithin the framework of the International Source Term Programme (ISTP), the VE...
International audienceThe capabilities of the Thermodynamic of Advanced Fuels – International Databa...
International audienceWithin the PLEIADES simulation platform co-developed by CEA, EDF and FRAMATOME...
International audienceThis paper describes the first VERDON test performed at the end of September 2...
Various countries engaged in the development and fabrication of modern HTGR fuel have initiated acti...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
International audienceIn this work, two different thermodynamic softwares, ANGE using the TBASE data...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
Abstract –Fuel irradiation testing and post-irradiation examination are currently in progress as par...
During a hypothetical severe nuclear accident involving a pressurised water reactor, it is of primar...