U236 Fission: Q Value & Symmetric Fission to 118Ru

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I have question regarding the fission of 236U,my question is why we have the Q value (185MeV) of the symmetric fission of U236 (two 118Ru) is less than the Q value (188MeV) for the fission into 96Sr and 140Xe
 
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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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