Sigma Basic Retrieval

Target: or Z: and A:

Select Reaction:
(n,*)
(n,total)
(n,elastic)
(n,inelastic)
(n,f)
(n,γ)
(n,2n)
(n,p)
(n,α)

And select quantity:
Cross sections
Resonance parameters
dσ/dω
dσ/dE
d²σ/dωdE
Covariances

Or select other ENDF topic:
Neutron cross section standards
Thermal neutron scattering
Photonuclear reactions
Proton reactions
Decay data
Neutron-induced fission yields
Spontaneous fission yields
Neutron-induced nu-bar's
All nu-bar's

Library:

All

ENDF/B-VII.0
(USA, 2006)

JEFF-3.1
(Europe, 2005)

JENDL-3.3
(Japan, 2002)

ENDF/B-VI.8
(USA, 2001)

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