Open AccessA Computational Method for Neutron Transport Problems in Toroidal Geometry
Author(s) -
Jungchung Jung
Publication year - 1977
Language(s) - English
Resource type - Reports
DOI - 10.2172/12036694
Subject(s) - torus , toroid , flux (metallurgy) , cylinder , physics , geometry , blanket , neutron flux , circumference , neutron , position (finance) , mechanics , point (geometry) , toroidal and poloidal , heat flux , closure (psychology) , plasma , nuclear physics , mathematics , materials science , heat transfer , market economy , finance , economics , metallurgy , composite material