Level energy(keV)   Spin & Parity       
       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 
        163.92           31.25         IT 
        818.51           99.58         IT 
       1048.07           99.82         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           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)
     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 
     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 
    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-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 
     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 
    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