56-Ba-137
Spin
Level energy(keV) Spin & Parity
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ground state 3/2+
6.61659E+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)
136.905827141 ± 0.000000303 (amu) [mass excess = -87721.453 ± 0.283 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-580.548 ± 1.632 (keV)
Strong Gamma-rays from Decay of Ba-137 (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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661.66 89.9 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 2.552 M 1
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Ba-137.
Figures of cross sections, Ba-137: 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-136 (Z= 56, A=136), MT=102 (n,γ)
Ba-137 (Z= 56, A=137), MT= 2 (Elastic scattering)
Ba-137 (Z= 56, A=137), MT= 4 (Inelastic scattering)
Ba-138 (Z= 56, A=138), MT= 16 (n,2n)
La-138 (Z= 57, A=138), MT= 28 (n,np)
La-138 (Z= 57, A=138), MT=104 (n,d)
La-139 (Z= 57, A=139), MT= 32 (n,nd)
La-139 (Z= 57, A=139), MT=105 (n,t)
Ce-140 (Z= 58, A=140), MT=107 (n,α)
Ce-141 (Z= 58, A=141), 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-137 U-235 Thermal 5.479180e-07 3.506670e-07
Ba-137 U-235 Fast 2.233520e-07 1.429460e-07
Ba-137 U-235 High 3.851810e-05 2.465160e-05
Ba-137 U-238 Fast 2.333680e-08 1.493560e-08
Ba-137 U-238 High 1.003490e-06 6.422380e-07
Ba-137 Pu-239 Thermal 1.866410e-05 1.194500e-05
Ba-137 Pu-239 Fast 1.448370e-05 9.269590e-06
Ba-137 Pu-239 High 1.655660e-04 1.059620e-04
Ba-137 Pu-241 Thermal 6.432390e-07 4.116730e-07
Ba-137 Pu-241 Fast 6.501730e-07 4.161110e-07
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Ba-137m U-235 Thermal 1.322110e-06 8.461470e-07
Ba-137m U-235 Fast 6.258950e-07 4.005730e-07
Ba-137m U-235 High 1.766670e-04 1.130670e-04
Ba-137m U-238 Fast 6.539620e-08 4.185360e-08
Ba-137m U-238 High 4.602610e-06 2.945670e-06
Ba-137m Pu-239 Thermal 4.503590e-05 2.882290e-05
Ba-137m Pu-239 Fast 4.058740e-05 2.597590e-05
Ba-137m Pu-239 High 7.593840e-04 4.860060e-04
Ba-137m Pu-241 Thermal 1.552120e-06 9.933540e-07
Ba-137m Pu-241 Fast 1.821970e-06 1.166060e-06
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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-137 U-235 Thermal 6.175470e-02 3.357740e-04
Ba-137 U-235 Fast 6.206910e-02 2.621760e-04
Ba-137 U-235 High 4.954390e-02 1.386880e-03
Ba-137 U-238 Fast 6.050980e-02 4.239710e-04
Ba-137 U-238 High 5.150780e-02 1.030170e-03
Ba-137 Pu-239 Thermal 6.611160e-02 3.317270e-04
Ba-137 Pu-239 Fast 6.587770e-02 3.303470e-04
Ba-137 Pu-239 High 4.547960e-02 2.727500e-03
Ba-137 Pu-241 Thermal 6.649210e-02 4.658690e-04
Ba-137 Pu-241 Fast 6.378910e-02 1.279800e-03
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Ba-137m U-235 Thermal 5.848130e-02 2.991100e-04
Ba-137m U-235 Fast 5.877930e-02 3.039430e-04
Ba-137m U-235 High 4.689030e-02 1.874390e-03
Ba-137m U-238 Fast 5.730270e-02 5.743870e-04
Ba-137m U-238 High 4.877720e-02 1.366250e-03
Ba-137m Pu-239 Thermal 6.259230e-02 3.154850e-04
Ba-137m Pu-239 Fast 6.237460e-02 4.384970e-04
Ba-137m Pu-239 High 4.294450e-02 3.430980e-03
Ba-137m Pu-241 Thermal 6.296750e-02 4.433090e-04
Ba-137m Pu-241 Fast 6.040780e-02 2.416770e-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