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Preservation of know-how on R&D activities in the field of radioactive waste management
Free accessBASE | 2017| -
Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides
British Library Online Contents | 2017| -
Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions
British Library Online Contents | 2016| -
Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions
Online Contents | 2016|Contributors: Kienzler, B -
Instant release of fission products in leaching experiments with high-burnup nuclear fuels in the framework of the Euratom project first- nuclides
Online Contents | 2016|Contributors: Kienzler, B -
Simulated alpha dose at the surface of the rim zone of spent nuclear fuel pellets
Free accessBASE | 2015| -
Simulation of alpha dose for predicting radiolytic species at the surface of spent nuclear fuel pellets
Free accessBASE | 2015| -
Radionuclide behaviour in the near-field of a geological repository for spent nuclear fuel
Free accessBASE | 2015| -
XAS and XRF investigation of an actual HAWC glass fragment obtained from the Karlsruhe vitrification plant (VEK)
British Library Online Contents | 2015| -
XAS and XRF investigation of an actual HAWC glass fragment obtained from the Karlsruhe vitrification plant (VEK)
British Library Online Contents | 2015|
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