ENDF/B-VII.1 evaluated neutron library.
ROSFOND evaluated neutron library.
CENDL-3.1 evaluated neutron library.
Pre-calculated integral quantities.
Energy-angle distributions (MF=6).
Visualization of covariances (MF=33 with LB=1,5; applies to ~80% of cases).
Visualization of resonance data (MF=32) is not yet available.
Thermal neutron cross sections & resonance integrals for (n,γ), (n,total fission).
Angular distributions of emitted neutrons (if available in MF=4).
Energy distributions of emitted neutrons and photons (if available in MF=5).
Computations (mathematical operations) on cross sections (MF=3).
Interactive access to ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, ENDF/B-VI.8 libraries.
Neutron cross section distributions (MF=3).
Experimental data in EXFOR format.