Add to ORKGSince 1993, the Institute for Transuranium Elements and Framatome APN GmbH have been co-operating in a study of the performance of PWR fuel at burn-ups beyond 60 MWd/kgHM. The fuel pellet and rod design characteristics were already described. The rods were standard PWR design for Siemens built reactors. Samples from the high power region of the fuel rod with an average burn-up of 97.8 MWd/kgHM were examined in previous studies.JRC.E.3-Materials researc
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radia...
At the peripheral region of high burnup fuel pellets, a crystallographic re-structuring is observed,...
Improvement of the nuclear fuel exploitation has been one of the main objectives of reactor technolo...
A study of the thermal conductivity of a commercial PWR fuel with an average pellet burn-up of 102 M...
Irradiation experience gained on fuel rods with burn-ups greater than 60 MWd/kgHM irradiated in the ...
A BWR design UO2 fuel irradiated to a burnup of 7.9% FIMA was selected for a careful calculational a...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2002.Includes ...
The maximum operating characteristics that can be achieved with the use of UO/sub 2/ as a reactor fu...
The thermal conductivity of UO2 and MOX LWR fuels decreases as a result of reactor burn-up. In this ...
Fuel performance models have been developed to assess the performance of ThO[subscript 2]-UO[subscri...
The thermal conductivity of irradiated nuclear fuels is usually extrapolated from the data acquired ...
AbstractVickers microhardness (HV0.1) and Young's modulus (E) measurements of LWR UO2 fuel at burn-u...
Vickers microhardness (HV0.1) and Young's modulus (E) measurements of LWR UO2 fuel at burn-up > 60 G...
International audienceThe validation range of the model in the TRANSURANUS fuel performance code for...
The fuel matrix and the cladding constitute the first barrier against radioactive fission product re...
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radia...
At the peripheral region of high burnup fuel pellets, a crystallographic re-structuring is observed,...
Improvement of the nuclear fuel exploitation has been one of the main objectives of reactor technolo...
A study of the thermal conductivity of a commercial PWR fuel with an average pellet burn-up of 102 M...
Irradiation experience gained on fuel rods with burn-ups greater than 60 MWd/kgHM irradiated in the ...
A BWR design UO2 fuel irradiated to a burnup of 7.9% FIMA was selected for a careful calculational a...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2002.Includes ...
The maximum operating characteristics that can be achieved with the use of UO/sub 2/ as a reactor fu...
The thermal conductivity of UO2 and MOX LWR fuels decreases as a result of reactor burn-up. In this ...
Fuel performance models have been developed to assess the performance of ThO[subscript 2]-UO[subscri...
The thermal conductivity of irradiated nuclear fuels is usually extrapolated from the data acquired ...
AbstractVickers microhardness (HV0.1) and Young's modulus (E) measurements of LWR UO2 fuel at burn-u...
Vickers microhardness (HV0.1) and Young's modulus (E) measurements of LWR UO2 fuel at burn-up > 60 G...
International audienceThe validation range of the model in the TRANSURANUS fuel performance code for...
The fuel matrix and the cladding constitute the first barrier against radioactive fission product re...
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radia...
At the peripheral region of high burnup fuel pellets, a crystallographic re-structuring is observed,...
Improvement of the nuclear fuel exploitation has been one of the main objectives of reactor technolo...