Many radiopharmacueticals are excreted from the body through the gastr
ointestinal (GI) tract. The doses to the walls of the organs involved
often are very significant. As significant fractions of the administer
ed activity pass through them, these organs may receive the highest do
ses in the body for many radiopharmaceuticals. The absorbed dose to th
ese walled organs, from activity in their contents, is typically calcu
lated as 50% of the average absorbed dose to the contents, for nonpene
trating emissions. The internal surface of the GI tract, and to a cert
ain extent the urinary bladder, is lined with a variable thickness of
mucus. In addition, the radiosensitive cell populations (crypt or stem
cells) are located at some depth into the mucosa. These two factors s
uggest that the surface dose, often used to characterize the clinicall
y relevant absorbed doses for walled organs, may represent an overesti
mate in some cases. Methods: In this study, the radiation transport co
de MCNP was used to simulate the deposition of energy from nonpenetrat
ing emissions of several radionuclides of interest: Y-90, Tc-99m, I-12
3 and I-131. Absorbed doses as a function of distance from the wall-co
ntents interface were calculated for three geometric shapes representi
ng different organs along the routes of excretion. Results: The absorb
ed dose from nonpenetrating emissions to the sensitive cell population
s was consistently lower than estimated by the standard model assumpti
on. The simulated absorbed doses to radiosensitive cells in the GI tra
ct for Tc-99m and I-123 are tenfold lower; those for I-131 are fivefol
d lower and those for Y-90 are 20% lower. Conclusion: This study demon
strates that the normally reported dose to the walls of hollow organs
probably should be modified to account for the attenuation of these no
npenetrating emissions in the linings of the walls. This study also de
monstrates that Monte Carlo codes continue to be useful in the evaluat
ion of the dose to sensitive cells in walled organs.