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September 17, 2026Nuclear TechnologyOpen Access

Multigroup Cross-Section Generation Using OpenMC Fixed-Source Neutron Transport Simulation for Spent TRISO Fuel

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BABrecken AllegoodRORodrigo G.G. de OliveiraJHJoshua Hanophy

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Allegood et al. (2026) studied this question.

synapsesocial.com/papers/6aabb7e75f706d05830e7433https://doi.org/10.1080/00295450.2026.2712102
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