57-La-139



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      7/2+                  
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)
     138.906356256 ± 0.000002438 (amu)  [mass excess = -87228.585 ± 2.271 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -278.382 ± 6.953 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, La-139.
     Figures of cross sections, La-139:  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
     La-138 (Z= 57, A=138), MT=102 (n,γ)
     La-139 (Z= 57, A=139), MT=  2 (Elastic scattering)
     La-139 (Z= 57, A=139), MT=  4 (Inelastic scattering)
     La-140 (Z= 57, A=140), MT= 16 (n,2n)
     Ce-140 (Z= 58, A=140), MT= 28 (n,np)
     Ce-140 (Z= 58, A=140), MT=104 (n,d)
     Ce-141 (Z= 58, A=141), MT= 32 (n,nd)
     Ce-141 (Z= 58, A=141), MT=105 (n,t)
     Pr-141 (Z= 59, A=141), MT=106 (n,3He)
     Pr-143 (Z= 59, A=143), MT= 22 (n,nα)
     Nd-143 (Z= 60, A=143), MT=112 (n,pα)

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-139    U-235   Thermal   2.266390e-07   1.450490e-07 
     La-139    U-235   Fast      8.901620e-08   5.697040e-08 
     La-139    U-235   High      6.671150e-05   4.269540e-05 
     La-139    U-238   Fast      8.103020e-09   5.185930e-09 
     La-139    U-238   High      8.669440e-07   5.548440e-07 
     La-139   Pu-239   Thermal   1.028840e-05   6.584560e-06 
     La-139   Pu-239   Fast      9.508460e-06   6.085410e-06 
     La-139   Pu-239   High      3.644960e-04   2.332770e-04 
     La-139   Pu-241   Thermal   2.280370e-07   1.459440e-07 
     La-139   Pu-241   Fast      2.578060e-07   1.649960e-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)
    -----------------------------------------------------------
     La-139    U-235   Thermal   6.404370e-02   4.579860e-04 
     La-139    U-235   Fast      6.330370e-02   3.423340e-04 
     La-139    U-235   High      4.816810e-02   1.925190e-03 
     La-139    U-238   Fast      5.676960e-02   5.710510e-04 
     La-139    U-238   High      5.056210e-02   1.012020e-03 
     La-139   Pu-239   Thermal   5.636130e-02   1.578430e-03 
     La-139   Pu-239   Fast      5.610600e-02   7.856570e-04 
     La-139   Pu-239   High      4.131380e-02   3.303090e-03 
     La-139   Pu-241   Thermal   6.218600e-02   1.243540e-03 
     La-139   Pu-241   Fast      6.302800e-02   1.766670e-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