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Questions and discussion about applications, input, output and general user topics
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Currently we are doing MCNP/DIF3D calculation for fast reactor analysis. For verification of the cross-sections generations, Serpent was used. The result above is the 9-groups capture cross sections for the active core region. Group 1 has the highest energy. There seems to be something wrong with Serpent cross sections in the group 1. In the high energy range, the capture cross-sections should be less dominant in the fuel region. Serpent 1 and 2 produced the same result, which is inconsistent with the others code.
- Jaakko Leppänen
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Donny, could you send me the input by e-mail?