Comparing Results of MCNP vs Geant4 for Shielding Design

terryphi
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I'm curious if anyone has any opinions in the results from MCNP vs Geant4 for shielding design.

I like that Geant4 uses a more modern syntax, but iv'e also heard that MCNP gives better results.
 
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Perhaps this helps?
http://www.irradiationpanel.org/docs/publications/MonteCarloCode%20Review_2010Publication.pdf
 
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Thread 'MCNP6 BURN Card Issue: Zero Burnup for Material in Fuel Assembly'

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...
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