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

Access to resources Favorite

Disclaimer: Any content in publications that violate the sovereignty, the constitution or regulations of the PRC is not accepted or approved by CNPIEC.

Previous Menu Next

Abstract