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I am a new entrant to OpenMC, trying to run an example test problem in ‘OpenMC/examples/lattice/simple’ to understand how OpenMC can be executed and offcourse its input/output structure. Earlier i built OpenMC from source in my linux system and created the executable and made sure its accessible from the CLI through the PATH environment. While executing this test i could not get python to understand the module ‘openmc’ receiving the following error.
(base) abalasub@freia013> python build_xml.py
Traceback (most recent call last):
File “build_xml.py”, line 1, in
import openmc
ModuleNotFoundError: No module named ‘openmc’

I suppose this could be a simple fix, but given that i am new to OpenMC i am kind of struggling. Probably some one could pointe me to the right direction.
Kind regards,

Hi Paul,
Thanks for that. It’s all working now. I could now be able to run my first simulation in OpenMC. I am currently trying to build a model that can perform neutron transport calculations and eventually compute the damage dose DPA. I would like to get your suggestions as to how this can be done in OpenMC.
Kind regards,

@abarun You can tally the damage-energy score in OpenMC, which uses the MT=444 data computed by NJOY. To get from the damage-energy score to dpa/sec, you can follow the guidance given in the NJOY/HEATR manual :

The damage output from HEATR is the damage energy production cross section (eV-barns). As in Eq. 160, multiplying by the density and flux gives eV/s. Dividing by 2Ed gives displacements/s. This result is often reduced by an efficiency factor (say 80%) to improve the fit to the empirical correlations.

Note that the tally in OpenMC will give you a quantity in [eV/source particle], which you’ll need to convert to [eV/sec] (see further guidance here ).