Quantifying Nuclear Reactions in Metal Hydrides at Low Energies
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70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Engineering topics
Publications and source records attributed to Persaud, Arun.
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This is a software package that makes it easier to handle MCNP, a neutron transport simulation toolkit, simulations. It helps with reading and writing output from MCNP and modifying the input files programmatically. Furthermore, it also allows the visualization of input geometry and of the results. Pymcnp provides access to these features using the Python programming language.