OpenMC/tests/regression_tests/microxs/test_reference_materials_hybrid.csv

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nuclides,reactions,groups,xs
U235,"(n,gamma)",1,0.1500301670375847
U235,fission,1,1.2578145727734291
O16,"(n,gamma)",1,0.00012069778439640312
O16,fission,1,0.0
Xe135,"(n,gamma)",1,0.014820264774863558
Xe135,fission,1,0.0