58-Ce-140



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)
     139.905443107 ± 0.000002340 (amu)  [mass excess = -88079.178 ± 2.180 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -3388.000 ± 6.000 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ce-140.
     Figures of cross sections, Ce-140:  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
     Ce-140 (Z= 58, A=140), MT=  2 (Elastic scattering)
     Ce-140 (Z= 58, A=140), MT=  4 (Inelastic scattering)
     Ce-141 (Z= 58, A=141), MT= 16 (n,2n)
     Ce-142 (Z= 58, A=142), MT= 17 (n,3n)
     Pr-141 (Z= 59, A=141), MT= 28 (n,np)
     Pr-141 (Z= 59, A=141), MT=104 (n,d)
     Pr-143 (Z= 59, A=143), MT= 33 (n,nt)
     Nd-142 (Z= 60, A=142), MT=106 (n,3He)
     Nd-143 (Z= 60, A=143), MT=107 (n,α)
     Nd-144 (Z= 60, A=144), MT= 22 (n,nα)
     Nd-145 (Z= 60, A=145), MT= 24 (n,2nα)

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)
    -----------------------------------------------------------
     Ce-140    U-235   Thermal   1.148170e-09   7.348300e-10 
     Ce-140    U-235   Fast      3.562650e-10   2.280090e-10 
     Ce-140    U-235   High      1.642250e-06   1.051040e-06 
     Ce-140    U-238   Fast      1.530570e-11   9.795650e-12 
     Ce-140    U-238   High      5.926460e-09   1.896470e-09 
     Ce-140   Pu-239   Thermal   1.309790e-07   8.382680e-08 
     Ce-140   Pu-239   Fast      5.539100e-08   1.772510e-08 
     Ce-140   Pu-239   High      1.940260e-05   1.241770e-05 
     Ce-140   Pu-241   Thermal   6.321020e-10   4.045460e-10 
     Ce-140   Pu-241   Fast      8.803380e-10   5.634160e-10 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Ce-140    U-235   Thermal   6.208720e-02   3.297520e-04 
     Ce-140    U-235   Fast      5.965020e-02   4.379210e-04 
     Ce-140    U-235   High      4.534850e-02   1.269580e-03 
     Ce-140    U-238   Fast      5.815660e-02   4.070880e-04 
     Ce-140    U-238   High      4.615310e-02   6.469000e-04 
     Ce-140   Pu-239   Thermal   5.363470e-02   5.366170e-04 
     Ce-140   Pu-239   Fast      5.331930e-02   3.735010e-04 
     Ce-140   Pu-239   High      3.845960e-02   2.306300e-03 
     Ce-140   Pu-241   Thermal   5.766940e-02   8.073390e-04 
     Ce-140   Pu-241   Fast      5.301400e-02   1.062230e-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