58-Ce-144



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)
     143.913652939 ± 0.000003354 (amu)  [mass excess = -80431.769 ± 3.124 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     318.646 ± 0.832 (keV) 
Strong Gamma-rays from Decay of Ce-144 (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 
  ----------------------------------------------------------
         40.98            0.26         B- 
         80.12            1.36         B- 
        133.51           11.09         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-           284.91 D 5       
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ce-144.
     Figures of cross sections, Ce-144:  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-143 (Z= 58, A=143), MT=102 (n,γ)
     Ce-144 (Z= 58, A=144), MT=  2 (Elastic scattering)
     Ce-144 (Z= 58, A=144), MT=  4 (Inelastic scattering)
     Nd-146 (Z= 60, A=146), MT=106 (n,3He)
     Nd-147 (Z= 60, A=147), MT=107 (n,α)
     Nd-148 (Z= 60, A=148), MT= 22 (n,nα)

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-144    U-235   Thermal   3.449310e-04   2.207560e-04 
     Ce-144    U-235   Fast      1.676440e-04   1.072920e-04 
     Ce-144    U-235   High      2.165780e-03   1.386110e-03 
     Ce-144    U-238   Fast      1.431530e-05   9.161820e-06 
     Ce-144    U-238   High      1.566810e-04   1.002760e-04 
     Ce-144   Pu-239   Thermal   1.163910e-03   7.449000e-04 
     Ce-144   Pu-239   Fast      1.642990e-03   1.051520e-03 
     Ce-144   Pu-239   High      5.061160e-03   3.239140e-03 
     Ce-144   Pu-241   Thermal   1.282310e-04   8.206760e-05 
     Ce-144   Pu-241   Fast      2.100620e-04   1.344400e-04 
    -----------------------------------------------------------
    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-144    U-235   Thermal   5.491390e-02   3.935420e-04 
     Ce-144    U-235   Fast      5.278540e-02   7.442290e-04 
     Ce-144    U-235   High      3.173400e-02   8.884940e-04 
     Ce-144    U-238   Fast      4.554260e-02   6.398150e-04 
     Ce-144    U-238   High      3.728310e-02   1.043840e-03 
     Ce-144   Pu-239   Thermal   3.738850e-02   2.618070e-04 
     Ce-144   Pu-239   Fast      3.671800e-02   3.672670e-04 
     Ce-144   Pu-239   High      2.682010e-02   1.072250e-03 
     Ce-144   Pu-241   Thermal   4.228540e-02   4.228990e-04 
     Ce-144   Pu-241   Fast      4.168350e-02   2.502800e-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