The Pij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method.
| Autor: | Abdullah, Ade Gafar, Nandiyanto, Asep Bayu Dani, Shafii, Mohammad Ali, Usman, Jakaria, Tongkukut, Seni H. J. |
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| Zdroj: | MATEC Web of Conferences; 8/17/2018, Vol. 197, pN.PAG-N.PAG, 4p |
| Databáze: | Complementary Index |
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