52-Te-126



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)
     125.903310886 ± 0.000001616 (amu)  [mass excess = -90065.330 ± 1.505 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -2154.027 ± 3.677 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Te-126.
     Figures of cross sections, Te-126:  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
     Te-125 (Z= 52, A=125), MT=102 (n,γ)
     Te-126 (Z= 52, A=126), MT=  2 (Elastic scattering)
     Te-126 (Z= 52, A=126), MT=  4 (Inelastic scattering)
     Te-127 (Z= 52, A=127), MT= 16 (n,2n)
     Te-128 (Z= 52, A=128), MT= 17 (n,3n)
     I -127 (Z= 53, A=127), MT= 28 (n,np)
     I -127 (Z= 53, A=127), MT=104 (n,d)
     I -129 (Z= 53, A=129), MT= 33 (n,nt)
     Xe-128 (Z= 54, A=128), MT=106 (n,3He)
     Xe-129 (Z= 54, A=129), MT=107 (n,α)
     Xe-130 (Z= 54, A=130), 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)
    -----------------------------------------------------------
     Te-126    U-235   Thermal   8.236890e-12   5.271610e-12 
     Te-126    U-235   Fast      1.247430e-11   7.983520e-12 
     Te-126    U-235   High      3.081220e-05   1.971990e-05 
     Te-126    U-238   Fast      8.733260e-14   5.589290e-14 
     Te-126    U-238   High      2.993260e-07   1.915690e-07 
     Te-126   Pu-239   Thermal   1.359780e-09   8.702630e-10 
     Te-126   Pu-239   Fast      1.179810e-09   7.550780e-10 
     Te-126   Pu-239   High      3.036870e-04   1.943600e-04 
     Te-126   Pu-241   Thermal   1.040170e-11   6.657070e-12 
     Te-126   Pu-241   Fast      1.269050e-10   8.121890e-11 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Te-126    U-235   Thermal   5.904590e-04   4.711250e-05 
     Te-126    U-235   Fast      9.725670e-04   7.808830e-05 
     Te-126    U-235   High      1.899320e-02   8.261540e-04 
     Te-126    U-238   Fast      5.396700e-04   3.247660e-05 
     Te-126    U-238   High      1.326420e-02   2.120360e-03 
     Te-126   Pu-239   Thermal   2.033670e-03   1.218420e-04 
     Te-126   Pu-239   Fast      2.676450e-03   1.603020e-04 
     Te-126   Pu-239   High      2.666130e-02   4.244700e-03 
     Te-126   Pu-241   Thermal   8.223020e-04   1.891470e-04 
     Te-126   Pu-241   Fast      2.240460e-03   2.463480e-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