Target:             or             Z:     and     A:
Ex: 56fe or fe56 or 56fe,60ni
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.1
   (USA, 2011)   		ENDF/B-VII.0
   (USA, 2006)   		JEFF-3.1
   (Europe, 2005)   		JENDL-4.0
   (Japan, 2010)    		JENDL-3.3
   (Japan, 2002)   		ROSFOND
   (Russia, 2008)   		CENDL-3.1
   (China, 2009)   		ENDF/B-VI.8
   (USA, 2001)  
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