58-Ce-142



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)
     141.909250375 ± 0.000002910 (amu)  [mass excess = -84532.731 ± 2.711 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -744.480 ± 2.387 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ce-142.
     Figures of cross sections, Ce-142:  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-141 (Z= 58, A=141), MT=102 (n,γ)
     Ce-142 (Z= 58, A=142), MT=  2 (Elastic scattering)
     Ce-142 (Z= 58, A=142), MT=  4 (Inelastic scattering)
     Ce-143 (Z= 58, A=143), MT= 16 (n,2n)
     Ce-144 (Z= 58, A=144), MT= 17 (n,3n)
     Pr-143 (Z= 59, A=143), MT= 28 (n,np)
     Pr-143 (Z= 59, A=143), MT=104 (n,d)
     Nd-144 (Z= 60, A=144), MT=106 (n,3He)
     Nd-145 (Z= 60, A=145), MT=107 (n,α)
     Nd-146 (Z= 60, A=146), MT= 22 (n,nα)
     Nd-147 (Z= 60, A=147), 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-142    U-235   Thermal   1.757210e-06   1.124610e-06 
     Ce-142    U-235   Fast      7.105330e-07   4.547410e-07 
     Ce-142    U-235   High      1.220770e-04   7.812950e-05 
     Ce-142    U-238   Fast      3.641350e-08   2.330460e-08 
     Ce-142    U-238   High      1.681830e-06   1.076370e-06 
     Ce-142   Pu-239   Thermal   3.566440e-05   2.282520e-05 
     Ce-142   Pu-239   Fast      3.674410e-05   2.351620e-05 
     Ce-142   Pu-239   High      5.678780e-04   3.634420e-04 
     Ce-142   Pu-241   Thermal   6.141000e-07   3.930240e-07 
     Ce-142   Pu-241   Fast      1.099170e-06   7.034710e-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)
    -----------------------------------------------------------
     Ce-142    U-235   Thermal   5.838840e-02   3.088980e-04 
     Ce-142    U-235   Fast      5.529330e-02   5.688180e-04 
     Ce-142    U-235   High      4.210370e-02   2.523380e-03 
     Ce-142    U-238   Fast      4.576380e-02   4.681520e-04 
     Ce-142    U-238   High      4.060940e-02   1.137250e-03 
     Ce-142   Pu-239   Thermal   4.928040e-02   2.466000e-04 
     Ce-142   Pu-239   Fast      4.753430e-02   3.329240e-04 
     Ce-142   Pu-239   High      3.109980e-02   2.486500e-03 
     Ce-142   Pu-241   Thermal   4.745300e-02   4.749960e-04 
     Ce-142   Pu-241   Fast      4.628410e-02   9.286770e-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