Binnary source file

hello dear sir
i am writing to you about my work on fixed source. In the user guide, i found that it is possible to use an external source in case of fixed source. this comes through using the binary source file. finally, any help such as a clear-cut clarification or exampls concerning this file. The question is how to create a binary source file?

Best regards

Josh Sayer

Hi Josh,

Normally, fission source information is written in the state point file, and can optionally be written in a separate source file with <source_point separate=“true” … /> (see full documentation on source_point here: http://mit-crpg.github.io/openmc/usersguide/input.html#source-point-element). The source point file can then be used as a starting source in a subsequent simulation using . However, there is no comparable capability for fixed source simulations.

If you really wanted to create a binary source file yourself, it is in theory possible. The data in the file is written starting with the integer -3 (indicating a source file) followed by N sets of 8 doubles: the weight, the position (x,y,z), the direction (u,v,w), and the energy.

If there is a particular functionality you would like to see, feel free to request it on this list.

Best regards,
Paul