THE USE OF MCNP CODE FOR RADIATION TRANSPORT AND DOSIMETRY CALCULATIONS IN TRAINING MEDICAL PHYSICS STUDENTS Abdullah Al Kafi, Nabil Maalej, Akhtar Abbas Naqvi Physics Department, King Fahd University of Petroleum and Minerals, Dhahran 31261, Saudi Arabia. Introduction.
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THE USE OF MCNP CODE FOR RADIATION TRANSPORT AND DOSIMETRY CALCULATIONS IN TRAINING MEDICAL PHYSICS STUDENTSAbdullah Al Kafi, Nabil Maalej, Akhtar Abbas NaqviPhysics Department, King Fahd University of Petroleum and Minerals, Dhahran 31261, Saudi Arabia
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Under charged particle equilibrium, the absorbed dose (D) to a medium can be calculated from the energy fluence and the mass energy absorption coefficient ;
For an ideal broad-beam geometry, the radiant energy of uncharged particles striking the detector through the attenuator at depth x is:
If a source emits N photons isotropically, the energy flounce at a distance r from the source and at a depth x in the attenuator;
Then the absorbed dose can be approximated by:
5 cm Lead Collimator
Percent depth dose (PDD): Percentage of the absorbed dose at any depth d to the maximum absorbed dose at reference depth dmax, along the central axis of the beam: