“…๐ s = photon scattering coefficient [cm -1 ] ๐
pf = Photon gain rate term from photofission reactions [cm -3 s -1 eV -1 ] ๐ p = photon source distribution (includes bremsstrahlung and neutron fission gammas) [cm -3 s -1 sr -1 eV -1 ] ๐ n = neutron angular flux [cm -2 s -1 sr -1 eV -1 ] ๐ด t = total macroscopic neutron cross section [cm -1 ] ๐ด s = scattering macroscopic neutron cross section [cm -1 ] ๐ = Neutron fission energy spectrum ๐ n = average number of neutrons produced per fission ๐ด f = fission macroscopic neutron cross section [cm -1 ] ๐ n = Neutron scalar flux [cm -2 s -1 eV -1 ] ๐ n = neutron source distribution (includes photoneutrons) [cm -3 s -1 sr -1 eV -1 ]. (Morel 1996, Wang 2018, Duderstadt and Hamilton 1976 The photofission term was extrapolated to be similar to a neutron fission term. The boundary conditions for the multiparticle (electron-photon-neutron) transport problem solved by MCNP are vacuum ๐ e ๐,๐ธ,ฮฉ = ๐ฟ ๐,ฮฉ = ๐ n ๐,๐ธ,ฮฉ = 0 for ฮฉ โข e s < 0 for all points r s on boundary surface S B .…”