Level energy(keV)   Spin & Parity       
       ground state      3/2+                  
       1.63930E+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)
     130.905084057 ± 0.000000236 (amu)  [mass excess = -88413.631 ± 0.220 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -354.752 ± 4.976 (keV) 
Strong Gamma-rays from Decay of Xe-131 (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 
        163.93            1.95         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           11.86 D 4        
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Xe-131.
     Figures of cross sections, Xe-131:  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-130 (Z= 54, A=130), MT=102 (n,γ)
     Xe-131 (Z= 54, A=131), MT=  2 (Elastic scattering)
     Xe-131 (Z= 54, A=131), MT=  4 (Inelastic scattering)
     Xe-132 (Z= 54, A=132), MT= 16 (n,2n)
     Xe-133 (Z= 54, A=133), MT= 17 (n,3n)
     Cs-133 (Z= 55, A=133), MT= 32 (n,nd)
     Cs-133 (Z= 55, A=133), MT= 41 (n,2np)
     Cs-133 (Z= 55, A=133), MT=105 (n,t)
     Cs-134 (Z= 55, A=134), MT= 33 (n,nt)
     Ba-134 (Z= 56, A=134), MT=107 (n,α)
     Ba-135 (Z= 56, A=135), 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)
     Xe-131    U-235   Thermal   1.433420e-09   9.173870e-10 
     Xe-131    U-235   Fast      8.545640e-10   5.469210e-10 
     Xe-131    U-235   High      1.986040e-06   1.271070e-06 
     Xe-131    U-238   Fast      1.123430e-11   3.594960e-12 
     Xe-131    U-238   High      2.381500e-09   7.620780e-10 
     Xe-131   Pu-239   Thermal   1.239190e-07   7.930860e-08 
     Xe-131   Pu-239   Fast      9.482240e-08   6.068620e-08 
     Xe-131   Pu-239   High      1.940190e-05   1.241720e-05 
     Xe-131   Pu-241   Thermal   2.344380e-09   1.500400e-09 
     Xe-131   Pu-241   Fast      2.515020e-09   1.609610e-09 
     Xe-131m   U-235   Thermal   3.458790e-09   2.213630e-09 
     Xe-131m   U-235   Fast      2.394730e-09   1.532630e-09 
     Xe-131m   U-235   High      9.109160e-06   5.829860e-06 
     Xe-131m   U-238   Fast      3.148170e-11   2.014820e-11 
     Xe-131m   U-238   High      1.092290e-08   6.990710e-09 
     Xe-131m  Pu-239   Thermal   2.990130e-07   1.913690e-07 
     Xe-131m  Pu-239   Fast      2.657190e-07   1.700600e-07 
     Xe-131m  Pu-239   High      8.898840e-05   5.695260e-05 
     Xe-131m  Pu-241   Thermal   5.656920e-09   3.620430e-09 
     Xe-131m  Pu-241   Fast      7.047790e-09   4.510590e-09 
    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-131    U-235   Thermal   2.890920e-02   1.445530e-04 
     Xe-131    U-235   Fast      3.217610e-02   2.261750e-04 
     Xe-131    U-235   High      4.108590e-02   1.150280e-03 
     Xe-131    U-238   Fast      3.292630e-02   3.295810e-04 
     Xe-131    U-238   High      3.995190e-02   5.596120e-04 
     Xe-131   Pu-239   Thermal   3.856360e-02   1.928200e-04 
     Xe-131   Pu-239   Fast      3.878300e-02   1.939190e-04 
     Xe-131   Pu-239   High      4.368600e-02   1.222740e-03 
     Xe-131   Pu-241   Thermal   3.101650e-02   4.341950e-04 
     Xe-131   Pu-241   Fast      3.362660e-02   6.724900e-04 
     Xe-131m   U-235   Thermal   3.180050e-04   8.688120e-05 
     Xe-131m   U-235   Fast      3.539390e-04   9.721540e-05 
     Xe-131m   U-235   High      4.609320e-04   1.245730e-04 
     Xe-131m   U-238   Fast      3.621900e-04   9.873430e-05 
     Xe-131m   U-238   High      4.394820e-04   1.204910e-04 
     Xe-131m  Pu-239   Thermal   4.244940e-04   1.162020e-04 
     Xe-131m  Pu-239   Fast      4.268750e-04   1.168600e-04 
     Xe-131m  Pu-239   High      5.683380e-04   1.716540e-04 
     Xe-131m  Pu-241   Thermal   3.411870e-04   9.454110e-05 
     Xe-131m  Pu-241   Fast      3.698990e-04   1.258730e-04 
    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