54-Xe-136



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      0+                    
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)
     135.907214484 ± 0.000000011 (amu)  [mass excess = -86429.152 ± 0.010 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -90.238 ± 1.877 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Xe-136.
     Figures of cross sections, Xe-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
     Xe-135 (Z= 54, A=135), MT=102 (n,γ)
     Xe-136 (Z= 54, A=136), MT=  2 (Elastic scattering)
     Xe-136 (Z= 54, A=136), MT=  4 (Inelastic scattering)
     Cs-136 (Z= 55, A=136), MT=103 (n,p)
     Cs-137 (Z= 55, A=137), MT= 28 (n,np)
     Cs-137 (Z= 55, A=137), MT=104 (n,d)
     Ba-140 (Z= 56, 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)
    -----------------------------------------------------------
     Xe-136    U-235   Thermal   2.189090e-02   9.850910e-03 
     Xe-136    U-235   Fast      1.708720e-02   1.879590e-03 
     Xe-136    U-235   High      2.174490e-02   6.958370e-03 
     Xe-136    U-238   Fast      2.444100e-03   1.564220e-03 
     Xe-136    U-238   High      8.054560e-03   5.154920e-03 
     Xe-136   Pu-239   Thermal   3.478650e-02   1.113170e-02 
     Xe-136   Pu-239   Fast      2.924130e-02   1.315860e-02 
     Xe-136   Pu-239   High      3.121210e-02   9.987870e-03 
     Xe-136   Pu-241   Thermal   1.083990e-02   3.468750e-03 
     Xe-136   Pu-241   Fast      1.080930e-02   3.458980e-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-136    U-235   Thermal   6.309660e-02   2.230600e-04 
     Xe-136    U-235   Fast      6.207190e-02   3.212780e-04 
     Xe-136    U-235   High      5.083260e-02   2.031750e-03 
     Xe-136    U-238   Fast      7.004610e-02   1.419220e-03 
     Xe-136    U-238   High      5.638990e-02   1.134340e-03 
     Xe-136   Pu-239   Thermal   7.048440e-02   7.050450e-04 
     Xe-136   Pu-239   Fast      6.942200e-02   6.943320e-04 
     Xe-136   Pu-239   High      5.472770e-02   2.187730e-03 
     Xe-136   Pu-241   Thermal   7.099870e-02   9.966970e-04 
     Xe-136   Pu-241   Fast      6.675090e-02   1.334750e-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