Level energy(keV)   Spin & Parity       
       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 
        661.66           89.9          IT 
     *: 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)
     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 
     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 
    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)
     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 
     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 
    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