56-Ba-136
Spin
Level energy(keV) Spin & Parity
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ground state 0+
2.03047E+03 7-
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)
135.904575727 ± 0.000000294 (amu) [mass excess = -88887.138 ± 0.274 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-2849.660 ± 53.172 (keV)
Strong Gamma-rays from Decay of Ba-136 (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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163.92 31.25 IT
818.51 99.58 IT
1048.07 99.82 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 0.3084 S 19
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ba-136.
Figures of cross sections, Ba-136: 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-135 (Z= 56, A=135), MT=102 (n,γ)
Ba-136 (Z= 56, A=136), MT= 2 (Elastic scattering)
Ba-136 (Z= 56, A=136), MT= 4 (Inelastic scattering)
Ba-137 (Z= 56, A=137), MT= 16 (n,2n)
Ba-138 (Z= 56, A=138), MT= 17 (n,3n)
La-138 (Z= 57, A=138), MT= 32 (n,nd)
La-138 (Z= 57, A=138), MT=105 (n,t)
La-139 (Z= 57, A=139), MT= 33 (n,nt)
Ce-140 (Z= 58, A=140), 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-136 U-235 Thermal 1.412020e-08 9.036920e-09
Ba-136 U-235 Fast 1.692940e-08 1.083480e-08
Ba-136 U-235 High 5.094890e-06 3.260730e-06
Ba-136 U-238 Fast 7.935760e-10 5.078880e-10
Ba-136 U-238 High 8.008920e-08 5.125720e-08
Ba-136 Pu-239 Thermal 1.476830e-06 9.451690e-07
Ba-136 Pu-239 Fast 1.267440e-06 8.111560e-07
Ba-136 Pu-239 High 4.042360e-05 2.587110e-05
Ba-136 Pu-241 Thermal 2.912730e-08 1.864150e-08
Ba-136 Pu-241 Fast 2.367340e-08 1.515100e-08
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Ba-136m U-235 Thermal 3.310450e-08 2.118690e-08
Ba-136m U-235 Fast 4.624010e-08 2.959370e-08
Ba-136m U-235 High 2.305370e-05 1.475440e-05
Ba-136m U-238 Fast 2.167530e-09 1.387220e-09
Ba-136m U-238 High 3.623930e-07 2.319320e-07
Ba-136m Pu-239 Thermal 3.462400e-06 2.215930e-06
Ba-136m Pu-239 Fast 3.461800e-06 2.215550e-06
Ba-136m Pu-239 High 1.829110e-04 1.170630e-04
Ba-136m Pu-241 Thermal 6.828850e-08 4.370460e-08
Ba-136m Pu-241 Fast 6.466020e-08 4.138250e-08
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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-136 U-235 Thermal 5.533910e-05 2.217290e-06
Ba-136 U-235 Fast 1.171020e-04 3.292620e-06
Ba-136 U-235 High 2.291300e-03 6.500280e-05
Ba-136 U-238 Fast 9.606540e-06 7.679830e-07
Ba-136 U-238 High 2.130930e-04 5.967500e-06
Ba-136 Pu-239 Thermal 9.791460e-04 2.740540e-05
Ba-136 Pu-239 Fast 1.235470e-03 2.470810e-05
Ba-136 Pu-239 High 7.761290e-03 3.168810e-04
Ba-136 Pu-241 Thermal 1.412500e-04 1.129690e-05
Ba-136 Pu-241 Fast 1.517440e-04 9.711630e-05
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Ba-136m U-235 Thermal 8.879800e-06 4.787300e-06
Ba-136m U-235 Fast 1.877240e-05 1.012060e-05
Ba-136m U-235 High 3.851530e-04 2.076460e-04
Ba-136m U-238 Fast 1.538740e-06 8.296340e-07
Ba-136m U-238 High 3.438650e-05 1.853840e-05
Ba-136m Pu-239 Thermal 1.593350e-04 8.589190e-05
Ba-136m Pu-239 Fast 2.003800e-04 1.080200e-04
Ba-136m Pu-239 High 1.388850e-03 7.502560e-04
Ba-136m Pu-241 Thermal 2.265270e-05 1.221330e-05
Ba-136m Pu-241 Fast 2.432960e-05 1.311710e-05
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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