54-Xe-129



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      1/2+                  
       2.36140E+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)
     128.90478086113 ± 0.00000000596 (amu)  [mass excess = -88696.05676 ± 0.00555 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1196.805 ± 4.555 (keV) 
Strong Gamma-rays from Decay of Xe-129 (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 
  ----------------------------------------------------------
         39.58            7.5          IT 
        196.56            4.59         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           8.88 D 2         
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Xe-129.
     Figures of cross sections, Xe-129:  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-128 (Z= 54, A=128), MT=102 (n,γ)
     Xe-129 (Z= 54, A=129), MT=  2 (Elastic scattering)
     Xe-129 (Z= 54, A=129), MT=  4 (Inelastic scattering)
     Xe-130 (Z= 54, A=130), MT= 16 (n,2n)
     Xe-131 (Z= 54, A=131), MT= 17 (n,3n)
     Ba-130 (Z= 56, A=130), MT=111 (n,2p)
     Ba-132 (Z= 56, A=132), 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-129    U-235   High      7.655500e-09   4.899510e-09 
     Xe-129    U-238   High      3.798850e-11   2.431260e-11 
     Xe-129   Pu-239   High      1.891630e-07   1.210640e-07 
    -----------------------------------------------------------
     Xe-129m   U-235   High      4.742000e-08   3.034880e-08 
     Xe-129m   U-238   High      2.353100e-10   1.505980e-10 
     Xe-129m  Pu-239   High      1.171720e-06   7.499010e-07 
    -----------------------------------------------------------
    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-129    U-235   Thermal   5.432070e-03   1.414680e-06 
     Xe-129    U-235   Fast      8.359600e-03   7.973980e-06 
     Xe-129    U-235   High      2.997060e-02   1.918110e-02 
     Xe-129    U-238   Fast      1.007730e-02   3.607380e-05 
     Xe-129    U-238   High      1.949470e-02   1.247660e-02 
     Xe-129   Pu-239   Thermal   1.321300e-02   5.013640e-04 
     Xe-129   Pu-239   Fast      1.405450e-02   4.558570e-04 
     Xe-129   Pu-239   High      2.941010e-02   1.882250e-02 
     Xe-129   Pu-241   Thermal   8.029930e-03   1.695850e-04 
     Xe-129   Pu-241   Fast      1.139130e-02   2.802370e-04 
    -----------------------------------------------------------
     Xe-129m   U-235   High      4.742000e-08   3.030380e-08 
     Xe-129m   U-238   High      2.353100e-10   1.504350e-10 
     Xe-129m  Pu-239   High      1.171720e-06   7.494150e-07 
    -----------------------------------------------------------
    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