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Title:
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Radiation dose-distribution calculations with MCNP at ECN
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Author(s):
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Published by:
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Publication date:
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ECN
NUCLEAIR
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1998
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ECN report number:
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Document type:
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ECN-I--97-039
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Other
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Number of pages:
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Full text:
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18
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Download PDF
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Abstract:
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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