Evaluated Nuclear Data File (ENDF) Retrieval & Plotting
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
d
2
σ/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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