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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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Incident neutron data
TENDL-2013
Cross sections
H
H1

Open General information
Open MT=1 : (n,total)
Open MT=2 : (z,elastic)
Open MT=102 : (z,γ)
Open MT=204 : (z,Xd)
Open MT=221 : free-gas scattering
Open MT=301 : KERMA total (energy balance)
Open MT=443 : total kinematic KERMA (kinematic limit)
Open MT=444 : total damage energy production cross section