Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides
| Autor: | Rosa Sureda, O. Roth, Zoltán Hózer, E. Slonszki, Thierry Mennecart, Ines Günther-Leopold, Karel Lemmens, Enzo Curti, A. Martínez-Torrents, Bernhard Kienzler, Daniel Serrano-Purroy, E. González-Robles |
|---|---|
| Jazyk: | angličtina |
| Rok vydání: | 2017 |
| Předmět: |
010302 applied physics
Fission products Nuclear and High Energy Physics Technology Radiochemistry chemistry.chemical_element 02 engineering and technology 021001 nanoscience & nanotechnology 01 natural sciences Fuel element failure Spent nuclear fuel Nuclear physics chemistry Materials Science(all) Nuclear Energy and Engineering Caesium 0103 physical sciences Oxidizing agent General Materials Science Leaching (metallurgy) Nuclide 0210 nano-technology MOX fuel ddc:600 |
| Zdroj: | Journal of nuclear materials, 484, 307–323 |
| ISSN: | 0022-3115 1873-4820 |
| Popis: | The instant release of fission products from high burn-up UO 2 fuels and one MOX fuel was investigated by means of leach tests. The samples covered PWR and BWR fuels at average rod burn-up in the range of 45–63 GWd/t HM and included clad fuel segments, fuel segments with opened cladding, fuel fragments and fuel powder. The tests were performed with sodium chloride – bicarbonate solutions under oxidizing conditions and, for one test, in reducing Ar/H 2 atmosphere. The iodine and cesium release could be partially explained by the differences in sample preparation, leading to different sizes and properties of the exposed surface areas. Iodine and cesium releases tend to correlate with FGR and linear power rating, but the scatter of the data is significant. Although the gap between the fuel and the cladding was closed in some high burn-up samples, fissures still provide possible preferential transport pathways. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|
Full Text from ScienceDirect