Generic method to assess transmutation feasibility for nuclear waste treatment and application to irradiated graphite
- DOI
- 10.1016/j.anucene.2022.109675
- Published
- 2023-05
- Container
- Annals of Nuclear Energy
- Publisher
- Elsevier BV
- Open access
- unknown
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Cite this work
BibTeX
@article{allodium:10.1016/j.anucene.2022.109675,
title = {Generic method to assess transmutation feasibility for nuclear waste treatment and application to irradiated graphite},
author = {Mathieu Rasson and Julien Fuchs and Grégoire Augé and Jean-Louis Quéri and Gérard Laurent},
year = {2023},
journal = {Annals of Nuclear Energy},
doi = {10.1016/j.anucene.2022.109675},
url = {https://doi.org/10.1016/j.anucene.2022.109675}
}RIS
TY - JOUR TI - Generic method to assess transmutation feasibility for nuclear waste treatment and application to irradiated graphite AU - Mathieu Rasson AU - Julien Fuchs AU - Grégoire Augé AU - Jean-Louis Quéri AU - Gérard Laurent PY - 2023 JO - Annals of Nuclear Energy DO - 10.1016/j.anucene.2022.109675 UR - https://doi.org/10.1016/j.anucene.2022.109675 ER -
APA
Rasson, M., Fuchs, J., Augé, G., Quéri, J., & Laurent, G. (2023). Generic method to assess transmutation feasibility for nuclear waste treatment and application to irradiated graphite. Annals of Nuclear Energy. https://doi.org/10.1016/j.anucene.2022.109675
Source records
- crossref · retrieved 2026-09-25T14:20:17.312Z