
MCNP6 calculation of neutron flux map in the httr during normal operation
Author(s) -
Hai Quan Ho,
E. Ishitsuka,
K. Iigaki
Publication year - 2022
Publication title -
vestnik. seriâ fizičeskaâ/habaršysy - a̋l-farabi atyndaġy k̦azak̦ memlekettik u̇lttyk̦ universitetì. fizika seriâsy
Language(s) - English
Resource type - Journals
eISSN - 2663-2276
pISSN - 1563-0315
DOI - 10.26577/rcph.2022.v82.i3.03
Subject(s) - neutron flux , nuclear engineering , flux (metallurgy) , nuclear physics , neutron , physics , neutron transport , monte carlo method , nuclear reactor core , nuclear reactor , helium , work (physics) , research reactor , materials science , atomic physics , thermodynamics , statistics , mathematics , engineering , metallurgy