56-Ba-140
Spin
Level energy(keV) Spin & Parity
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ground state 0+
Mass (The Ame2012 atomic mass evaluation (II) by M.Wang, G.Audi, A.H.Wapstra, F.G.Kondev, M.MacCormick, X.Xu, and B.Pfeiffer
Chinese Physics C36 p. 1603-2014, December 2012)
139.910605730 ± 0.000008527 (amu) [mass excess = -83270.226 ± 7.943 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1048.019 ± 8.020 (keV)
Strong Gamma-rays from Decay of Ba-140 (Compiled from ENSDF as of March 2011)
[ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
γ-ray energy(keV) Intensity(%) Decay mode
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29.97 14.1 B-
162.66 6.22 B-
537.26 24.39 B-
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*: relative, ~ approximate, ? calculated or estimatted
>: greater than or equal to, <: less than or equal to
[ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
Decay mode Half-life
B- 12.7527 D 23
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ba-140.
Figures of cross sections, Ba-140: type-1: type-2: type-3.
type-1: total, elastic and inelastic scattering, capture and fision cross sections
type-2: same as type-1 but cross sections are averaged in 70 energy group intervals
type-3: threshold reaction cross sections
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Ba-140 (Z= 56, A=140), MT= 2 (Elastic scattering)
Ba-140 (Z= 56, A=140), MT= 4 (Inelastic scattering)
La-140 (Z= 57, A=140), MT=103 (n,p)
Ce-142 (Z= 58, A=142), MT=106 (n,3He)
Ce-143 (Z= 58, A=143), MT=107 (n,α)
Ce-144 (Z= 58, A=144), MT= 22 (n,nα)
Fission Yields for Fission Products in JENDL-4.0 Fission Yield Data
- Neutron-induced Fission Yields (from main actinide nuclides) - Independent Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
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Ba-140 U-235 Thermal 4.876180e-03 1.121520e-03
Ba-140 U-235 Fast 2.350270e-03 1.504170e-03
Ba-140 U-235 High 9.568600e-03 4.305870e-03
Ba-140 U-238 Fast 2.664900e-04 1.705530e-04
Ba-140 U-238 High 1.376800e-03 8.811520e-04
Ba-140 Pu-239 Thermal 1.479940e-02 3.403860e-03
Ba-140 Pu-239 Fast 9.166140e-03 5.866320e-03
Ba-140 Pu-239 High 1.371280e-02 4.388080e-03
Ba-140 Pu-241 Thermal 1.752090e-03 1.121340e-03
Ba-140 Pu-241 Fast 1.712040e-03 1.095710e-03
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
- Neutron-induced Fission Yields (from main actinide nuclides) - Cumulative Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
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Ba-140 U-235 Thermal 6.203520e-02 6.310450e-04
Ba-140 U-235 Fast 5.964820e-02 6.115650e-04
Ba-140 U-235 High 4.501240e-02 1.260170e-03
Ba-140 U-238 Fast 5.815630e-02 4.070860e-04
Ba-140 U-238 High 4.611180e-02 6.463200e-04
Ba-140 Pu-239 Thermal 5.353260e-02 7.497360e-04
Ba-140 Pu-239 Fast 5.322050e-02 7.453450e-04
Ba-140 Pu-239 High 3.703210e-02 1.480560e-03
Ba-140 Pu-241 Thermal 5.766520e-02 1.614550e-03
Ba-140 Pu-241 Fast 5.301010e-02 4.244780e-03
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
→ Neutron-induced and Spontaneous Fission Yields of all nuclides in JENDL-4.0 Fission Yield Data