Preliminary studies on neutron conversion coefficients calculated with MCNPX in NORMAN voxel phantom

Area of Science:

• Medical Physics
• Radiation Dosimetry
• Computational Modeling

Background:

• The International Commission on Radiological Protection (ICRP) is revising recommendations for effective dose calculation.
• Accurate organ absorbed doses are crucial for effective dose estimation in radiation protection.
• Existing voxel phantoms like ADAM, EVA, and VIP-MAN have limitations in detailed anatomical representation.

Purpose of the Study:

• To introduce and utilize the modified NORMAN-05 voxel phantom for neutron dosimetry.
• To calculate neutron conversion coefficients for a range of energies (thermal to 20 MeV).
• To compare preliminary results with existing published data for validation.

Main Methods:

• Development of the NORMAN-05 voxel phantom, incorporating salivary glands and detailed skeletal structures.
• Utilizing the MCNPX Monte Carlo code for neutron transport simulations.
• Performing calculations for antero-posterior (AP) and postero-anterior (PA) irradiation geometries.

Main Results:

• The NORMAN-05 phantom provides a more detailed anatomical model, particularly for skeletal dosimetry.
• Preliminary neutron conversion coefficients have been calculated for various energies and angles.
• Initial comparisons with published data indicate the potential accuracy of the NORMAN-05 phantom.

Conclusions:

• The NORMAN-05 voxel phantom is a valuable tool for advanced neutron dosimetry.
• This model aids in refining effective dose calculations in radiation protection.
• Further validation and application of the NORMAN-05 phantom are warranted.