52-Te-130



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)
     129.906222748 ± 0.000000012 (amu)  [mass excess = -87352.947 ± 0.011 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -416.792 ± 3.168 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Te-130.
     Figures of cross sections, Te-130:  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-129 (Z= 52, A=129), MT=102 (n,γ)
     Te-130 (Z= 52, A=130), MT=  2 (Elastic scattering)
     Te-130 (Z= 52, A=130), MT=  4 (Inelastic scattering)
     Te-132 (Z= 52, A=132), MT= 17 (n,3n)
     I -130 (Z= 53, A=130), MT=103 (n,p)
     I -131 (Z= 53, A=131), MT= 28 (n,np)
     I -131 (Z= 53, A=131), MT=104 (n,d)
     Xe-132 (Z= 54, A=132), MT=106 (n,3He)
     Xe-133 (Z= 54, A=133), MT=107 (n,α)
     Xe-134 (Z= 54, A=134), MT= 22 (n,nα)
     Cs-134 (Z= 55, A=134), MT=112 (n,pα)
     Cs-135 (Z= 55, A=135), MT= 45 (n,npα)
     Cs-135 (Z= 55, A=135), MT=117 (n,dα)

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-130    U-235   Thermal   5.778400e-04   9.245440e-05 
     Te-130    U-235   Fast      2.396950e-04   1.534050e-04 
     Te-130    U-235   High      6.691690e-03   4.282680e-03 
     Te-130    U-238   Fast      5.291970e-07   3.386860e-07 
     Te-130    U-238   High      1.186380e-03   7.592780e-04 
     Te-130   Pu-239   Thermal   2.051050e-03   1.312680e-03 
     Te-130   Pu-239   Fast      1.954660e-03   1.250980e-03 
     Te-130   Pu-239   High      1.450940e-02   4.643020e-03 
     Te-130   Pu-241   Thermal   1.158190e-05   7.412390e-06 
     Te-130   Pu-241   Fast      9.592790e-06   6.139380e-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)
    -----------------------------------------------------------
     Te-130    U-235   Thermal   1.810220e-02   3.620570e-04 
     Te-130    U-235   Fast      1.818600e-02   7.568850e-04 
     Te-130    U-235   High      3.591460e-02   2.864400e-03 
     Te-130    U-238   Fast      1.938620e-02   1.174990e-03 
     Te-130    U-238   High      3.214970e-02   5.081220e-03 
     Te-130   Pu-239   Thermal   2.367370e-02   1.888440e-03 
     Te-130   Pu-239   Fast      2.463530e-02   1.475920e-03 
     Te-130   Pu-239   High      4.346680e-02   4.772460e-03 
     Te-130   Pu-241   Thermal   1.822380e-02   2.001030e-03 
     Te-130   Pu-241   Fast      1.865120e-02   1.490570e-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