The validation range of the model in the TRANSURANUS fuel performance code for calculating the radial power density and burnup in UO2 fuel has been extended from 64 MWd/kgHM up to 102 MWd/kgHM, thereby improving also its precision. In addition, the first verification of calculations with post-irradiation examination data is reported for LWR-MOX fuel with a rod average burn-up up to 45 MWd/kgHM. The extension covers the inclusion of new isotopes in order to account for the production of 238Pu. The corresponding one-group cross-sections used in the equations rely on results obtained with ALEPH, a new Monte Carlo burn-up code. The experimental verification is based on electron probe microanalysis (EPMA) and on secondary ion mass spectrometry (...
The prediction of fuel rod behaviour in a Light Water Reactor at high bumup is difficult because the...
In general, the verification and validation of a fuel performance code like TRANSURANUS consists of ...
Recent developments of the TRANSURANUS code concering the modelling and simulation of nuclear fuel r...
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radia...
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radia...
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radia...
International audienceThe validation range of the model in the TRANSURANUS fuel performance code for...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The Transuranus Burn-up (TUBRNP) model for (Th,Pu) O2 and (Th,U) O2 fuels is described and validated...
The present work concerns the study of Plutonium and some Minor Actinides (MAs) radial distribution ...
In the paper we present an update of verification calculations for the TRANSURANUS fuel performance ...
The prediction of fuel rod behaviour in a Light Water Reactor at high bumup is difficult because the...
In general, the verification and validation of a fuel performance code like TRANSURANUS consists of ...
Recent developments of the TRANSURANUS code concering the modelling and simulation of nuclear fuel r...
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radia...
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radia...
The validation range of the model in the TRANSURANUS fuel performance code for calculating the radia...
International audienceThe validation range of the model in the TRANSURANUS fuel performance code for...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main...
The Transuranus Burn-up (TUBRNP) model for (Th,Pu) O2 and (Th,U) O2 fuels is described and validated...
The present work concerns the study of Plutonium and some Minor Actinides (MAs) radial distribution ...
In the paper we present an update of verification calculations for the TRANSURANUS fuel performance ...
The prediction of fuel rod behaviour in a Light Water Reactor at high bumup is difficult because the...
In general, the verification and validation of a fuel performance code like TRANSURANUS consists of ...
Recent developments of the TRANSURANUS code concering the modelling and simulation of nuclear fuel r...