ECN publication
Radiation dose-distribution calculations with MCNP at ECN
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ECN report number: Document type:
ECN-I--97-039 Other
Number of pages: Full text:
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Patient dependent dose calculations, including the calculation of dosedistributions, have been recommended at the June 1997 meeting of the Medical Internal Radiation Dose (MIRD) committee. 3D-Monte Carlo programmes are suitable for calculating the volume-integrated dose over an organ, but it is not yet feasible to calculate dose distributions within an organ. With an ECN modification of the Monte Carlo N-Particle Transport Code (MCNP) this has become possible in principle. In this report a demonstration is given of the use of this modification by calculating the dose distribution in the liver due to a distributed gamma source. 3 refs.

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