Cargando…
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...
| Autores principales: | , , , |
|---|---|
| Formato: | Online Artículo Texto |
| Lenguaje: | English |
| Publicado: |
Elsevier
2020
|
| Materias: | |
| 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 |