Add to ORKGThis work focuses on the Instant Release Fraction modeling of several leaching experiments performed with a High Burn-up Spent Fuel of 60 MWd/kgU. Experimental results from powder samples from different parts of the fuel and cladded fuel (CS) segment samples were evaluated. Data were obtained by using different experimental devices, both batch (static) and continuous flow system (dynamic). Uranium, technetium and cesium release have been studied by using a kinetic model which consists of three functions for first order kinetics representing different parts of the fuel. A good fit has been obtained in all the cases.JRC.E.5-Nuclear chemistr
The Leaking Fuel Experiment test facility was designed to simulate the activity release from spent l...
A physics-based model is developed for analysing the coupled phenomena of fission gas swelling and r...
A non-equilibrium thermodynamic model is developed for the dissolution response of uranium oxide spe...
The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercise...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
The leaching of a high-burn-up spent nuclear fuel (48 GWd/tU) has been studied in a carbonate-contai...
This paper presents simulations of four tests performed on medium to high burnup fuel during the VER...
This paper presents simulations of the VERDON 1 and RT6 tests (temperature increase up to fuel-clad ...
Three models have been developed and applied in the performance assessment of a final repository. Th...
The impact of burn-up on the instant release fraction (IRF) from spent fuel was studied using very h...
The contact of the coolant with the fuel pin during irradiation produces a gradient of temperature i...
International audienceA physico-chemical model developed for spent fuel alteration was integrated in...
Fuel treatment is planned at the Argonne National Laboratory on EBR-II spent fuel. The electrochemic...
In the first part of the paper, experimental results for the Xe depletion in the matrix of high burn...
The dissolution behavior of an unirradiated chemical analogue of spent nuclear fuel (SIMFUEL) has be...
The Leaking Fuel Experiment test facility was designed to simulate the activity release from spent l...
A physics-based model is developed for analysing the coupled phenomena of fission gas swelling and r...
A non-equilibrium thermodynamic model is developed for the dissolution response of uranium oxide spe...
The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercise...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
The leaching of a high-burn-up spent nuclear fuel (48 GWd/tU) has been studied in a carbonate-contai...
This paper presents simulations of four tests performed on medium to high burnup fuel during the VER...
This paper presents simulations of the VERDON 1 and RT6 tests (temperature increase up to fuel-clad ...
Three models have been developed and applied in the performance assessment of a final repository. Th...
The impact of burn-up on the instant release fraction (IRF) from spent fuel was studied using very h...
The contact of the coolant with the fuel pin during irradiation produces a gradient of temperature i...
International audienceA physico-chemical model developed for spent fuel alteration was integrated in...
Fuel treatment is planned at the Argonne National Laboratory on EBR-II spent fuel. The electrochemic...
In the first part of the paper, experimental results for the Xe depletion in the matrix of high burn...
The dissolution behavior of an unirradiated chemical analogue of spent nuclear fuel (SIMFUEL) has be...
The Leaking Fuel Experiment test facility was designed to simulate the activity release from spent l...
A physics-based model is developed for analysing the coupled phenomena of fission gas swelling and r...
A non-equilibrium thermodynamic model is developed for the dissolution response of uranium oxide spe...