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Here an interesting paper, about using a modified OpenMC code to score a MCNP F8-like tally for calibration detector purposes.
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Effect of the various tritium breeding materials on the tritium breeding ratio in ARC fusion reactor
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Here’s my paper using OpenMC
https://authors.elsevier.com/c/1hPud15hWOqqOR
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Here is my paper on improving the transmutation rates of minor actinides in a lead-cooled fast reactor (analyses conducted using OpenMC):
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This is my paper on TRISO particle reactivity reduction using OpenMC:
An alternative approach for excess reactivity control of TRISO particles
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