Level energy(keV)   Spin & Parity       
       ground state      3/2+                  
       5.26562E+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)
     134.907227780 ± 0.000004455 (amu)  [mass excess = -86416.766 ± 4.150 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     1165.048 ± 4.071 (keV) 
Strong Gamma-rays from Decay of Xe-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 
        249.79           90.           B- 
        407.99            0.36         B- 
        608.18            2.9          B- 
        526.56           80.56         IT 
        786.9           4.E-03         B- 
       1133.            3.E-04         B- 
       1358.            2.E-04         B- 
     *: 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 
       B-           9.14 H 2         
       B-           15.29 M 5        
       IT           15.29 M 5        
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Xe-135.
     Figures of cross sections, Xe-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
     Xe-134 (Z= 54, A=134), MT=102 (n,γ)
     Xe-135 (Z= 54, A=135), MT=  2 (Elastic scattering)
     Xe-135 (Z= 54, A=135), MT=  4 (Inelastic scattering)
     Xe-136 (Z= 54, A=136), MT= 16 (n,2n)
     Cs-135 (Z= 55, A=135), MT=103 (n,p)
     Cs-136 (Z= 55, A=136), MT= 28 (n,np)
     Cs-136 (Z= 55, A=136), MT=104 (n,d)
     Cs-137 (Z= 55, A=137), MT= 32 (n,nd)
     Cs-137 (Z= 55, A=137), MT= 41 (n,2np)
     Cs-137 (Z= 55, A=137), MT=105 (n,t)
     Ba-138 (Z= 56, A=138), MT=107 (n,α)

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)
     Xe-135    U-235   Thermal   7.507970e-04   4.504780e-05 
     Xe-135    U-235   Fast      8.010140e-04   1.842330e-04 
     Xe-135    U-235   High      2.599310e-03   4.158890e-04 
     Xe-135    U-238   Fast      7.067870e-05   4.523430e-05 
     Xe-135    U-238   High      6.001780e-04   6.601950e-05 
     Xe-135   Pu-239   Thermal   3.124130e-03   1.249650e-04 
     Xe-135   Pu-239   Fast      3.840130e-03   2.304080e-04 
     Xe-135   Pu-239   High      3.985130e-03   1.793310e-03 
     Xe-135   Pu-241   Thermal   6.649330e-04   5.319470e-05 
     Xe-135   Pu-241   Fast      6.610580e-04   4.230780e-04 
     Xe-135m   U-235   Thermal   1.811650e-03   1.086990e-04 
     Xe-135m   U-235   Fast      2.244670e-03   1.436590e-03 
     Xe-135m   U-235   High      1.192200e-02   3.815030e-03 
     Xe-135m   U-238   Fast      1.980620e-04   1.267600e-04 
     Xe-135m   U-238   High      2.752770e-03   1.761770e-03 
     Xe-135m  Pu-239   Thermal   7.538430e-03   4.824590e-03 
     Xe-135m  Pu-239   Fast      1.076110e-02   6.887120e-03 
     Xe-135m  Pu-239   High      1.827810e-02   8.225140e-03 
     Xe-135m  Pu-241   Thermal   1.604460e-03   1.026850e-03 
     Xe-135m  Pu-241   Fast      1.852470e-03   1.185580e-03 
    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)
     Xe-135    U-235   Thermal   6.523010e-02   4.733700e-04 
     Xe-135    U-235   Fast      6.578910e-02   6.782690e-04 
     Xe-135    U-235   High      5.674920e-02   3.851060e-03 
     Xe-135    U-238   Fast      6.922760e-02   8.067420e-04 
     Xe-135    U-238   High      5.832340e-02   1.328860e-03 
     Xe-135   Pu-239   Thermal   7.604770e-02   7.608870e-04 
     Xe-135   Pu-239   Fast      7.538660e-02   2.380780e-03 
     Xe-135   Pu-239   High      6.184480e-02   1.888020e-02 
     Xe-135   Pu-241   Thermal   7.162300e-02   1.436860e-03 
     Xe-135   Pu-241   Fast      7.054040e-02   1.422420e-03 
     Xe-135m   U-235   Thermal   1.219580e-02   1.157360e-03 
     Xe-135m   U-235   Fast      1.264130e-02   2.879950e-03 
     Xe-135m   U-235   High      1.891920e-02   3.009020e-03 
     Xe-135m   U-238   Fast      1.162460e-02   1.257910e-03 
     Xe-135m   U-238   High      1.186150e-02   2.694140e-03 
     Xe-135m  Pu-239   Thermal   1.837290e-02   5.623160e-03 
     Xe-135m  Pu-239   Fast      2.083340e-02   6.405440e-03 
     Xe-135m  Pu-239   High      2.483700e-02   7.743220e-03 
     Xe-135m  Pu-241   Thermal   1.309640e-02   2.285690e-03 
     Xe-135m  Pu-241   Fast      1.312460e-02   3.003470e-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