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ENDF EXFOR CINDA Resonances Decay Covariances
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n-induced cross sections γ-induced cross sections p-induced cross sections d-induced cross sections t-induced cross sections h-induced cross sections α-induced cross sections
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Base
Incident neutron data
FENDL-2.1 MG
Cross sections
Mo
Mo92
T=300.0°K
sigma0=1.0

Open MT=1 : (n,total) (Legendre order 0)
Open MT=1 : (n,total) (Legendre order 1)
Open MT=2 : (z,elastic)
Open MT=102 : (z,γ)
Open MT=301 : KERMA total (energy balance)
Open MT=443 : total kinematic KERMA (kinematic limit)
Open MT=444 : total damage energy production cross section
Open Flux: MT=1 : (n,total) (Legendre order 0)
Open Flux: MT=1 : (n,total) (Legendre order 1)
Open Flux: MT=2 : (z,elastic)
Open Flux: MT=102 : (z,γ)
Open Flux: MT=301 : KERMA total (energy balance)
Open Flux: MT=443 : total kinematic KERMA (kinematic limit)
Open Flux: MT=444 : total damage energy production cross section