Fission products and nuclear fuel behaviour under severe accident conditions part 2: Fuel behaviour in the VERDON-1 sample
| العنوان: | Fission products and nuclear fuel behaviour under severe accident conditions part 2: Fuel behaviour in the VERDON-1 sample |
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| المؤلفون: | A. Gallais-During, J. Lamontagne, C. Le Gall, E. Hanus, G. Ducros, E. Geiger, Yves Pontillon |
| المساهمون: | CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA) |
| المصدر: | Journal of Nuclear Materials Journal of Nuclear Materials, 2017, 495, pp.49-57. ⟨10.1016/j.jnucmat.2017.08.002⟩ |
| بيانات النشر: | Elsevier BV, 2017. |
| سنة النشر: | 2017 |
| مصطلحات موضوعية: | Fuel-cladding interactions, Nuclear and High Energy Physics, [PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th], Nuclear engineering, Sample (statistics), 02 engineering and technology, [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], Experimental laboratory, 01 natural sciences, 010305 fluids & plasmas, 0103 physical sciences, General Materials Science, Light-water reactor, LWR, Fuel behaviour, Severe accident, Fission products, VERDON tests, Nuclear fuel, Radioactive waste, Post-test characterisations, 021001 nanoscience & nanotechnology, ISTP, Nuclear Energy and Engineering, UO2 irradiated fuel, Environmental science, 0210 nano-technology, Nuclear chemistry |
| الوصف: | International audience; Within the framework of the International Source Term Programme (ISTP), the VERDON programme aims at quantifying the source term of radioactive materials in case of a hypothetical severe accident in a light water reactor (LWR). Tests were performed in a new experimental laboratory (VERDON) built in the LECA-STAR facility (CEA Cadarache). The VERDON-1 test was devoted to the study of a high burn-up UO$_2$ fuel and FP releases at very high temperature ($\approx$2600°C) in a reducing atmosphere. Post-test qualitative and quantitative characterisations of the VERDON-1 sample led to the proposal of a scenario explaining the phenomena occurring during the experimental sequence. Hence, the fuel and the cladding may have interacted which led to the melting of UO$_2$-ZrO$_2$ alloy. Although no relocation was observed during the test, it may have been imminent. |
| تدمد: | 0022-3115 |
| URL الوصول: | https://explore.openaire.eu/search/publication?articleId=doi_dedup___::afb9e8e5eef9e147b4e8e2d6b815e237 https://doi.org/10.1016/j.jnucmat.2017.08.002 |
| حقوق: | OPEN |
| رقم الأكسشن: | edsair.doi.dedup.....afb9e8e5eef9e147b4e8e2d6b815e237 |
| قاعدة البيانات: | OpenAIRE |
| تدمد: | 00223115 |
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