56-Ba-135
Spin
Level energy(keV) Spin & Parity
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ground state 3/2+
2.68218E+02 11/2-
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)
134.905688375 ± 0.000000294 (amu) [mass excess = -87850.713 ± 0.274 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1207.205 ± 9.430 (keV)
Strong Gamma-rays from Decay of Ba-135 (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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268.22 16. IT
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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
IT 28.7 H 2
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ba-135.
Figures of cross sections, Ba-135: 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-134 (Z= 56, A=134), MT=102 (n,γ)
Ba-135 (Z= 56, A=135), MT= 2 (Elastic scattering)
Ba-135 (Z= 56, A=135), MT= 4 (Inelastic scattering)
Ba-136 (Z= 56, A=136), MT= 16 (n,2n)
Ba-137 (Z= 56, A=137), MT= 17 (n,3n)
La-138 (Z= 57, A=138), MT= 33 (n,nt)
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-135 U-235 Thermal 2.234960e-10 1.430380e-10
Ba-135 U-235 Fast 6.430230e-11 4.115340e-11
Ba-135 U-235 High 5.341520e-07 3.418570e-07
Ba-135 U-238 Fast 5.946030e-12 3.805450e-12
Ba-135 U-238 High 3.458470e-09 2.213420e-09
Ba-135 Pu-239 Thermal 3.574030e-08 2.287380e-08
Ba-135 Pu-239 Fast 3.339560e-08 2.137320e-08
Ba-135 Pu-239 High 4.554920e-06 2.915150e-06
Ba-135 Pu-241 Thermal 3.809620e-10 2.438160e-10
Ba-135 Pu-241 Fast 4.467640e-10 2.859290e-10
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Ba-135m U-235 Thermal 5.392890e-10 3.451460e-10
Ba-135m U-235 Fast 1.801930e-10 1.153230e-10
Ba-135m U-235 High 2.449940e-06 1.567960e-06
Ba-135m U-238 Fast 1.666250e-11 1.066390e-11
Ba-135m U-238 High 1.586260e-08 1.015210e-08
Ba-135m Pu-239 Thermal 8.624030e-08 5.519380e-08
Ba-135m Pu-239 Fast 9.358390e-08 5.989370e-08
Ba-135m Pu-239 High 2.089160e-05 1.337060e-05
Ba-135m Pu-241 Thermal 9.192490e-10 5.883190e-10
Ba-135m Pu-241 Fast 1.251960e-09 8.012530e-10
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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-135 U-235 Thermal 6.523550e-02 2.760680e-04
Ba-135 U-235 Fast 6.579160e-02 5.123310e-04
Ba-135 U-235 High 5.735910e-02 3.438100e-03
Ba-135 U-238 Fast 6.922840e-02 6.621210e-04
Ba-135 U-238 High 5.835060e-02 1.170420e-03
Ba-135 Pu-239 Thermal 7.617450e-02 5.345800e-04
Ba-135 Pu-239 Fast 7.551280e-02 3.790490e-04
Ba-135 Pu-239 High 6.379710e-02 7.013300e-03
Ba-135 Pu-241 Thermal 7.163080e-02 7.211880e-04
Ba-135 Pu-241 Fast 7.054840e-02 1.000770e-03
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Ba-135m U-235 Thermal 5.392890e-10 3.451460e-10
Ba-135m U-235 Fast 1.801930e-10 1.153230e-10
Ba-135m U-235 High 2.449940e-06 1.565640e-06
Ba-135m U-238 Fast 1.666250e-11 1.066000e-11
Ba-135m U-238 High 1.586260e-08 1.014110e-08
Ba-135m Pu-239 Thermal 8.624030e-08 5.519380e-08
Ba-135m Pu-239 Fast 9.358390e-08 5.989370e-08
Ba-135m Pu-239 High 2.089160e-05 1.336190e-05
Ba-135m Pu-241 Thermal 9.192490e-10 5.882240e-10
Ba-135m Pu-241 Fast 1.251960e-09 8.012530e-10
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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