57-La-146



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      2-                    
       ground state(+X)  (6-)                  
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)
     145.925875174 ± 0.000036014 (amu)  [mass excess = -69046.831 ± 33.547 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     6588.235 ± 34.401 (keV) 
Strong Gamma-rays from Decay of La-146 (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 
  ----------------------------------------------------------
        258.42           94.95         B- 
        409.78           75.           B- 
        514.65           23.77         B- 
  ----------------------------------------------------------
        258.47           63.7          B- 
        702.28            6.43         B- 
        924.58            7.45         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-           10.0 S 1         
       B-           6.27 S 10        
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0 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)
    -----------------------------------------------------------
     La-146    U-235   Thermal   5.310800e-03   3.398910e-03 
     La-146    U-235   Fast      4.282130e-03   2.740560e-03 
     La-146    U-235   High      2.407990e-03   1.541110e-03 
     La-146    U-238   Fast      4.108190e-03   2.629240e-03 
     La-146    U-238   High      2.916580e-03   1.866610e-03 
     La-146   Pu-239   Thermal   4.145400e-03   2.653060e-03 
     La-146   Pu-239   Fast      3.625060e-03   2.320040e-03 
     La-146   Pu-239   High      1.231960e-03   7.884510e-04 
     La-146   Pu-241   Thermal   5.522490e-03   3.534390e-03 
     La-146   Pu-241   Fast      4.765610e-03   3.049990e-03 
    -----------------------------------------------------------
     La-146m   U-235   Thermal   9.565390e-03   6.121840e-03 
     La-146m   U-235   Fast      8.975240e-03   5.744150e-03 
     La-146m   U-235   High      8.438810e-03   5.400830e-03 
     La-146m   U-238   Fast      8.610650e-03   5.510820e-03 
     La-146m   U-238   High      1.022120e-02   6.541530e-03 
     La-146m  Pu-239   Thermal   7.466370e-03   4.778480e-03 
     La-146m  Pu-239   Fast      7.598040e-03   4.862740e-03 
     La-146m  Pu-239   High      4.317400e-03   2.763130e-03 
     La-146m  Pu-241   Thermal   9.946680e-03   6.365870e-03 
     La-146m  Pu-241   Fast      9.988610e-03   6.392710e-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)
    -----------------------------------------------------------
     La-146    U-235   Thermal   1.451100e-02   9.287050e-03 
     La-146    U-235   Fast      1.591130e-02   1.018320e-02 
     La-146    U-235   High      4.220330e-03   2.696640e-03 
     La-146    U-238   Fast      2.504620e-02   1.598500e-02 
     La-146    U-238   High      1.199370e-02   7.639550e-03 
     La-146   Pu-239   Thermal   6.539490e-03   4.185270e-03 
     La-146   Pu-239   Fast      5.881190e-03   3.763960e-03 
     La-146   Pu-239   High      1.731730e-03   1.107420e-03 
     La-146   Pu-241   Thermal   1.478660e-02   9.451510e-03 
     La-146   Pu-241   Fast      1.357900e-02   8.689280e-03 
    -----------------------------------------------------------
     La-146m   U-235   Thermal   9.565390e-03   6.121840e-03 
     La-146m   U-235   Fast      8.975240e-03   5.744150e-03 
     La-146m   U-235   High      8.438810e-03   5.392830e-03 
     La-146m   U-238   Fast      8.610650e-03   5.508800e-03 
     La-146m   U-238   High      1.022120e-02   6.534450e-03 
     La-146m  Pu-239   Thermal   7.466370e-03   4.778480e-03 
     La-146m  Pu-239   Fast      7.598040e-03   4.862740e-03 
     La-146m  Pu-239   High      4.317400e-03   2.761340e-03 
     La-146m  Pu-241   Thermal   9.946680e-03   6.364840e-03 
     La-146m  Pu-241   Fast      9.988610e-03   6.392710e-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