Name |
Release year |
Characteristics |
JENDL Actinoid File 2008
(JENDL/AC-2008) |
2008 |
Neutron-induced reaction data for 79 nuclides from Ac (Z=89) to Fm (Z=100).
Numerical data |
JENDL Activation Cross Section File 96
(JENDL/A-96) |
1996 |
For activity estimation of reactor material. The data
of 233 nuclides and 1246 reactions.
Numerical data |
JENDL (α,n) Reaction Data File 2003
(JENDL/AN-2003) |
2003 |
Neutron production cross sections of 13 nuclides for
α-particle induced reactions.
Numerical data |
JENDL (α,n) Reaction Data File 2005
(JENDL/AN-2005) |
2005 |
Neutron production cross sections of 17 nuclides for α-particle induced
reactions.
Numerical data |
JENDL Dosimetry File 91
(JENDL/D-91) |
1991 |
The data of 61 reactions for reactor dosimetry and their
covariance.
Numerical data |
JENDL Dosimetry File 99
(JENDL/D-99) |
1999 |
The revised version of Dosimetry File 91. The data of
67 reactions for reactor dosimetry and their covariance
data.
Numerical data |
JENDL FP decay Data File 2000
(JENDL/FPD-2000) |
2000 |
Decay data for 1229 fission product nuclides.
Numerical data |
JENDL Fusion File 99
(JENDL/F-99) |
1999 |
For fusion neutronics. The data for 92 nuclides are stored
Numerical data |
JENDL Gas-Production Cross Section File 91
(JENDL/G-91) |
1991 |
The cross section data of gas production reactions such
as (n,p) and (n,α) of reactor material induced by neutrons.
Numerical data |
JENDL High Energy File 2004
(JENDL/HE-2004) |
2004 |
Neutron- and proton-induced reaction data up to 3 GeV for 66 nuclides.
Numerical data |
JENDL High Energy File 2007
(JENDL/HE-2007) |
2007 |
Neutron- and proton-induced reaction data up to 3 GeV for 106 nuclides.
Numerical data |
JENDL Photonuclear Data File 2004
(JENDL/PD-2004) |
2004 |
Photon-induced reaction data up to 140 MeV for 68 nuclides.
Numerical data |