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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
TENDL-2019
Cross sections
Be
Be7

Open General information
Open MT=1 : (n,total)
Open MT=2 : (z,elastic)
Open MT=203 : (z,Xp)
Open MT=204 : (z,Xd)
Open MT=207 : (z,Xa)
Open MT=221 : free-gas scattering
Open MT=301 : KERMA total (energy balance)
Open MT=442 : total photon KERMA contribution
Open MT=443 : total kinematic KERMA (kinematic limit)
Open MT=444 : total damage energy production cross section
Open MT=600 : (z,p0)
Open MT=601 : (z,p1)
Open MT=650 : (z,d0)
Open MT=800 : (z,α0)