Assistance Needed with OpenMC to Calculate Air Kerma and Mean Glandular Dose for Breast Voxel Phantom

AI Thread Summary
A radiation protection student seeks guidance on using OpenMC to calculate air kerma and mean glandular dose for a breast voxel phantom. The student has prepared the phantom and geometry, defining the source as photons at 30 keV, but is struggling with mesh creation. The process involves two steps: creating the mesh and then applying a mesh filter using the MeshFilter function. OpenMC supports different mesh types, including RegularMesh and CylindricalMesh, which require specific input grids. The discussion highlights the importance of following tutorials for effective mesh implementation.
REMS R
Messages
2
Reaction score
0
Hello everyone

I am a radiation protection student and need assistance with OpenMC. I have a breast voxel phantom and I want to calculate the air kerma to determine the mean glandular dose. I'm not sure what steps to follow to achieve this. Could someone guide me through the process?
 
Engineering news on Phys.org
Hello,

Could you add more details? what have you done up to now? Have you created the geometry and the source?
 
mark_bose said:
Hello,

Could you add more details? what have you done up to now? Have you created the geometry and the source?
The phantom and geometry are ready, and I have defined the source as photons with an energy of 30 keV. However, I am stuck at the step of building the mesh.
 
The creation of the mesh is done in two steps: first you create the mesh itself than you create the mesh filter using the MeshFilter function.

OpenMC offers various options for the mesh (RegularMesh, CylindricalMesh...).
For example here you can find the function for cylindrical mesh. It needs as input the radial, axial and angular grids. that are provided as list or arrays.
Once you have created the mesh you need to create a mesh filter.

In this tutorial they show how to use the RegularMesh function
 
Hello, I'm currently trying to compare theoretical results with an MCNP simulation. I'm using two discrete sets of data, intensity (probability) and linear attenuation coefficient, both functions of energy, to produce an attenuated energy spectrum after x-rays have passed through a thin layer of lead. I've been running through the calculations and I'm getting a higher average attenuated energy (~74 keV) than initial average energy (~33 keV). My guess is I'm doing something wrong somewhere...
Back
Top