MCNP Monte Carlo calculations with an extended cross section data set
have been performed for an anthropomorphic MIRD (ADAM) phantom in the
neutron energy range between 20 and 100 MeV. The irradiation condition
s vary from 0 degrees (frontal incidence) up to 75 degrees to the left
side of the MIRD phantom. From the fluence calculations, organ doses
and dose equivalents are derived using the kerma approximation. The qu
ality factor as function of neutron energy for the calculation of effe
ctive dose equivalent, H-E, is derived from initial charged particle s
pectra produced in an ICRU tissue element by primary neutrons. Above 2
0 MeV an approximation was applied. Resulting organ doses and dose equ
ivalents are compared with a data set published by Nabelssi and Hertel
(1993).