Know of an open source Boltzmann solver for photon transport?

AI Thread Summary
Several groups have developed Boltzmann solvers for photon and neutron transport simulations, but there is a lack of publicly available open source code. The inquiry specifically seeks open source Boltzmann solvers, distinguishing them from Monte Carlo methods. There is also interest in non-commercially locked software that could be adapted for radiotherapy simulations using photon and electron cross section databases. Participants are encouraged to share any relevant projects or contacts that could assist in this endeavor. The goal is to find suitable software for applications in medical physics rather than nuclear engineering.
flo55
Messages
2
Reaction score
0
Many groups have created Boltzmann solvers for photon/neutron transport simulations of reactors over the years - but has anyone released their code? I am specifically interested in Boltzmann solvers, not Monte Carlo based calculations. If you know of any open source projects, please let me know.

Of course if you know of a group with software that is not officially open source (but also not commercially locked), then we may instead be able to come up with some other agreement, so don't hesitate to point me in their direction.
 
Last edited:
Engineering news on Phys.org
One note to add:

My intentions are to adapt the software for radiotherapy simulation applications using photon and electron cross section databases, so I will not be competing in the field of nuclear physics/engineering.
 
Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information(power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.) for Material 2 is zero, while Material 1...
Hi everyone, I'm a complete beginner with MCNP and trying to learn how to perform burnup calculations. Right now, I'm feeling a bit lost and not sure where to start. I found the OECD-NEA Burnup Credit Calculational Criticality Benchmark (Phase I-B) and was wondering if anyone has worked through this specific benchmark using MCNP6? If so, would you be willing to share your MCNP input file for it? Seeing an actual working example would be incredibly helpful for my learning. I'd be really...
Back
Top