The Pij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method

Publisher： Edp Sciences

E-ISSN： 2261-236x|197|issue|02006-02006

ISSN： 2261-236x

Source： MATEC Web of conference, Vol.197, Iss.issue, 2018-09, pp. : 02006-02006

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