58-Ce-141



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)
     140.908280674 ± 0.000002340 (amu)  [mass excess = -85436.002 ± 2.180 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     580.420 ± 1.053 (keV) 
Strong Gamma-rays from Decay of Ce-141 (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 
  ----------------------------------------------------------
        145.44           48.29         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-           32.508 D 1       
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ce-141.
     Figures of cross sections, Ce-141:  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=102 (n,γ)
     Ce-141 (Z= 58, A=141), MT=  2 (Elastic scattering)
     Ce-141 (Z= 58, A=141), MT=  4 (Inelastic scattering)
     Ce-142 (Z= 58, A=142), MT= 16 (n,2n)
     Ce-143 (Z= 58, A=143), MT= 17 (n,3n)
     Pr-141 (Z= 59, A=141), MT=103 (n,p)
     Pr-143 (Z= 59, A=143), MT= 32 (n,nd)
     Pr-143 (Z= 59, A=143), MT=105 (n,t)
     Nd-143 (Z= 60, A=143), MT=106 (n,3He)
     Nd-144 (Z= 60, A=144), MT=107 (n,α)
     Nd-145 (Z= 60, A=145), MT= 22 (n,nα)
     Nd-146 (Z= 60, A=146), 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-141    U-235   Thermal   4.982070e-08   3.188520e-08 
     Ce-141    U-235   Fast      3.213360e-07   1.028280e-07 
     Ce-141    U-235   High      1.743390e-05   1.115770e-05 
     Ce-141    U-238   Fast      9.053380e-10   5.794160e-10 
     Ce-141    U-238   High      1.101190e-07   7.047670e-08 
     Ce-141   Pu-239   Thermal   2.289640e-06   1.465370e-06 
     Ce-141   Pu-239   Fast      2.459600e-06   1.574140e-06 
     Ce-141   Pu-239   High      1.314750e-04   8.414420e-05 
     Ce-141   Pu-241   Thermal   2.290370e-08   1.465840e-08 
     Ce-141   Pu-241   Fast      3.687230e-08   2.359830e-08 
    -----------------------------------------------------------
    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-141    U-235   Thermal   5.838400e-02   5.909730e-04 
     Ce-141    U-235   Fast      5.937240e-02   1.669940e-03 
     Ce-141    U-235   High      4.492480e-02   2.692210e-03 
     Ce-141    U-238   Fast      5.337390e-02   1.494250e-03 
     Ce-141    U-238   High      4.386260e-02   8.775730e-04 
     Ce-141   Pu-239   Thermal   5.246490e-02   1.049390e-03 
     Ce-141   Pu-239   Fast      5.146670e-02   1.441190e-03 
     Ce-141   Pu-239   High      3.562640e-02   2.136240e-03 
     Ce-141   Pu-241   Thermal   4.906770e-02   6.868810e-04 
     Ce-141   Pu-241   Fast      5.071770e-02   4.060420e-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