<div>I am trying to solve a transport process of multi group energies in a neutron beam...</div> <div>Can GetDP be of any help in this...?</div> <div>My further step will be to include anelastic interaction of neutrons via positive or negative source terms to model fission induced neutron production as well as neutron absorption,as well as a photon transport process in an ionizing gas coupled to the ffirst problem, so: does GetDP allows for ALE meshing strategies...?</div> <div> </div> <div>Thanks in advance</div> <div> </div> <div>Alex</div><p>
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