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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
ENDF/B-VIII.0
Cross sections
Ra
Ra224

Open General information
Open MT=1 : (n,total)
Open MT=2 : (z,elastic)
Open MT=4 : (z,n')
Open MT=16 : (z,2n)
Open MT=17 : (z,3n)
Open MT=37 : (z,4n)
Open MT=51 : (z,n'1)
Open MT=52 : (z,n'2)
Open MT=53 : (z,n'3)
Open MT=54 : (z,n'4)
Open MT=55 : (z,n'5)
Open MT=56 : (z,n'6)
Open MT=57 : (z,n'7)
Open MT=58 : (z,n'8)
Open MT=59 : (z,n'9)
Open MT=60 : (z,n'10)
Open MT=61 : (z,n'11)
Open MT=91 : (z,nc) continuum inelastic
Open MT=102 : (z,γ)
Open MT=221 : free-gas scattering
Open MT=301 : KERMA total (energy balance)
Open MT=302 : KERMA elastic
Open MT=303 : KERMA non-elastic
Open MT=304 : KERMA inelastic
Open MT=318 : KERMA fission
Open MT=402 : KERMA radiative capture
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=445 : elastic damage energy production cross section
Open MT=446 : inelastic damage energy production cross section
Open MT=447 : neutron disappearance damage energy production cross section