60-Nd-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)
     143.910092974 ± 0.000001952 (amu)  [mass excess = -83747.855 ± 1.819 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -2331.923 ± 2.650 (keV) 
Decay data(Chart of the Nuclides 2014)
     Decay mode     Half-life 
       A            2.29E+15 Y 16    
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Nd-144.
     Figures of cross sections, Nd-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
     Nd-143 (Z= 60, A=143), MT=102 (n,γ)
     Nd-144 (Z= 60, A=144), MT=  2 (Elastic scattering)
     Nd-144 (Z= 60, A=144), MT=  4 (Inelastic scattering)
     Nd-145 (Z= 60, A=145), MT= 16 (n,2n)
     Nd-146 (Z= 60, A=146), MT= 17 (n,3n)
     Nd-147 (Z= 60, A=147), MT= 37 (n,4n)
     Pm-147 (Z= 61, A=147), MT= 33 (n,nt)
     Sm-147 (Z= 62, A=147), MT=107 (n,α)
     Sm-148 (Z= 62, A=148), MT= 22 (n,nα)
     Sm-149 (Z= 62, A=149), 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)
    -----------------------------------------------------------
     Nd-144    U-235   Thermal   9.554780e-11   1.051030e-11 
     Nd-144    U-235   Fast      1.287340e-10   4.119490e-11 
     Nd-144    U-235   High      5.527570e-08   3.537650e-08 
     Nd-144    U-238   Fast      5.101900e-14   3.265220e-14 
     Nd-144    U-238   High      5.185640e-11   3.318810e-11 
     Nd-144   Pu-239   Thermal   1.369780e-09   8.766620e-10 
     Nd-144   Pu-239   Fast      5.679080e-10   1.817310e-10 
     Nd-144   Pu-239   High      1.460950e-06   9.350060e-07 
     Nd-144   Pu-241   Thermal   2.680430e-12   1.715480e-12 
     Nd-144   Pu-241   Fast      1.029230e-11   6.587050e-12 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Nd-144    U-235   Thermal   5.491400e-02   2.090880e-04 
     Nd-144    U-235   Fast      5.278550e-02   3.818590e-04 
     Nd-144    U-235   High      3.176880e-02   8.894690e-04 
     Nd-144    U-238   Fast      4.554260e-02   3.245120e-04 
     Nd-144    U-238   High      3.728350e-02   1.043850e-03 
     Nd-144   Pu-239   Thermal   3.739220e-02   1.309950e-04 
     Nd-144   Pu-239   Fast      3.672360e-02   2.571530e-04 
     Nd-144   Pu-239   High      2.706230e-02   1.081930e-03 
     Nd-144   Pu-241   Thermal   4.228550e-02   2.961470e-04 
     Nd-144   Pu-241   Fast      4.168370e-02   8.346660e-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