Level energy(keV)   Spin & Parity       
       ground state      3/2+                  
       2.33221E+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)
     132.905910751 ± 0.000002576 (amu)  [mass excess = -87643.571 ± 2.400 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     427.360 ± 2.400 (keV) 
Strong Gamma-rays from Decay of Xe-133 (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 
        233.22           10.           IT 
         79.62            0.27         B- 
         81.00           38.           B- 
        160.61            0.07         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-           5.243 D 1        
       IT           2.19 D 1         
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Xe-133.
     Figures of cross sections, Xe-133:  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-132 (Z= 54, A=132), MT=102 (n,γ)
     Xe-133 (Z= 54, A=133), MT=  2 (Elastic scattering)
     Xe-133 (Z= 54, A=133), MT=  4 (Inelastic scattering)
     Xe-134 (Z= 54, A=134), MT= 16 (n,2n)
     Xe-135 (Z= 54, A=135), MT= 17 (n,3n)
     Cs-133 (Z= 55, A=133), MT=103 (n,p)
     Cs-134 (Z= 55, A=134), MT= 28 (n,np)
     Cs-134 (Z= 55, A=134), MT=104 (n,d)
     Cs-135 (Z= 55, A=135), MT= 32 (n,nd)
     Cs-135 (Z= 55, A=135), MT= 41 (n,2np)
     Cs-135 (Z= 55, A=135), MT=105 (n,t)
     Cs-136 (Z= 55, A=136), MT= 33 (n,nt)
     Ba-135 (Z= 56, A=135), MT=106 (n,3He)
     Ba-136 (Z= 56, A=136), MT=107 (n,α)
     Ba-137 (Z= 56, A=137), 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-133    U-235   Thermal   7.465480e-06   4.479290e-07 
     Xe-133    U-235   Fast      1.492070e-05   8.952430e-07 
     Xe-133    U-235   High      3.081490e-04   1.972150e-04 
     Xe-133    U-238   Fast      4.312180e-06   2.759800e-06 
     Xe-133    U-238   High      3.104560e-05   9.934610e-06 
     Xe-133   Pu-239   Thermal   1.266940e-04   1.393640e-05 
     Xe-133   Pu-239   Fast      1.638490e-04   9.830940e-06 
     Xe-133   Pu-239   High      6.841090e-04   4.378300e-04 
     Xe-133   Pu-241   Thermal   2.534860e-06   1.622310e-06 
     Xe-133   Pu-241   Fast      5.303350e-06   3.394150e-06 
     Xe-133m   U-235   Thermal   1.801400e-05   1.152890e-05 
     Xe-133m   U-235   Fast      4.181210e-05   2.675980e-05 
     Xe-133m   U-235   High      1.413350e-03   9.045450e-04 
     Xe-133m   U-238   Fast      1.208400e-05   7.733720e-06 
     Xe-133m   U-238   High      1.423940e-04   9.113170e-05 
     Xe-133m  Pu-239   Thermal   3.057080e-04   1.956530e-04 
     Xe-133m  Pu-239   Fast      4.591500e-04   2.938560e-04 
     Xe-133m  Pu-239   High      3.137730e-03   2.008150e-03 
     Xe-133m  Pu-241   Thermal   6.116540e-06   3.914590e-06 
     Xe-133m  Pu-241   Fast      1.486150e-05   9.511350e-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)
     Xe-133    U-235   Thermal   6.689360e-02   4.281190e-02 
     Xe-133    U-235   Fast      6.710080e-02   4.294460e-02 
     Xe-133    U-235   High      5.536570e-02   3.538450e-02 
     Xe-133    U-238   Fast      6.760790e-02   4.326900e-02 
     Xe-133    U-238   High      6.024070e-02   3.851150e-02 
     Xe-133   Pu-239   Thermal   7.015560e-02   4.489960e-02 
     Xe-133   Pu-239   Fast      6.970150e-02   4.460900e-02 
     Xe-133   Pu-239   High      4.863220e-02   3.098430e-02 
     Xe-133   Pu-241   Thermal   6.730560e-02   4.306420e-02 
     Xe-133   Pu-241   Fast      6.454980e-02   4.131190e-02 
     Xe-133m   U-235   Thermal   1.943810e-03   1.244050e-03 
     Xe-133m   U-235   Fast      1.972680e-03   1.262510e-03 
     Xe-133m   U-235   High      2.958310e-03   1.890480e-03 
     Xe-133m   U-238   Fast      1.958720e-03   1.253580e-03 
     Xe-133m   U-238   High      1.872330e-03   1.196940e-03 
     Xe-133m  Pu-239   Thermal   2.313740e-03   1.480790e-03 
     Xe-133m  Pu-239   Fast      2.448610e-03   1.567110e-03 
     Xe-133m  Pu-239   High      4.428270e-03   2.832230e-03 
     Xe-133m  Pu-241   Thermal   1.944270e-03   1.244000e-03 
     Xe-133m  Pu-241   Fast      1.873310e-03   1.198920e-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