Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code

The paper describes a data library containing material composition of spent nuclear fuel. The data is extracted from burnup and depletion calculations with the Serpent2 code. The simulations were done with a PWR fuel pin cell geometry, for both initial UO(2) and MOX fuel load for a wide range of ini...

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Detalles Bibliográficos
Autores principales: Elter, Zsolt, Balkeståhl, Li Pöder, Branger, Erik, Grape, Sophie
Formato: Online Artículo Texto
Lenguaje:English
Publicado: Elsevier 2020
Materias:
Data Article
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC7588691/
https://www.ncbi.nlm.nih.gov/pubmed/33134449
http://dx.doi.org/10.1016/j.dib.2020.106429

Internet

https://www.ncbi.nlm.nih.gov/pmc/articles/PMC7588691/
https://www.ncbi.nlm.nih.gov/pubmed/33134449
http://dx.doi.org/10.1016/j.dib.2020.106429

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