60-Nd-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)
     141.907728996 ± 0.000001953 (amu)  [mass excess = -85949.886 ± 1.820 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -4807.827 ± 23.653 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Nd-142.
     Figures of cross sections, Nd-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
     Nd-142 (Z= 60, A=142), MT=  2 (Elastic scattering)
     Nd-142 (Z= 60, A=142), MT=  4 (Inelastic scattering)
     Nd-143 (Z= 60, A=143), MT= 16 (n,2n)
     Nd-144 (Z= 60, A=144), MT= 17 (n,3n)
     Sm-144 (Z= 62, A=144), MT= 44 (n,n2p)
     Sm-144 (Z= 62, A=144), MT=106 (n,3He)
     Sm-144 (Z= 62, A=144), MT=115 (n,pd)
     Sm-147 (Z= 62, A=147), MT= 24 (n,2nα)
     Sm-148 (Z= 62, A=148), MT= 25 (n,3nα)

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-142    U-235   High      6.999600e-11   4.479740e-11 
     Nd-142   Pu-239   Thermal   3.459460e-13   2.214050e-13 
     Nd-142   Pu-239   Fast      4.019350e-13   2.572380e-13 
     Nd-142   Pu-239   High      5.443530e-09   3.483860e-09 
    -----------------------------------------------------------
    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-142    U-235   Thermal   4.621910e-11   7.763580e-14 
     Nd-142    U-235   Fast      1.566510e-11   3.475520e-14 
     Nd-142    U-235   High      3.044390e-07   1.945390e-07 
     Nd-142    U-238   Fast      7.461580e-13   1.530350e-16 
     Nd-142    U-238   High      4.594270e-10   4.248820e-13 
     Nd-142   Pu-239   Thermal   1.089690e-08   6.973980e-09 
     Nd-142   Pu-239   Fast      1.159670e-08   7.421870e-09 
     Nd-142   Pu-239   High      5.147960e-06   3.289610e-06 
     Nd-142   Pu-241   Thermal   2.740010e-11   5.724590e-17 
     Nd-142   Pu-241   Fast      5.664830e-11   5.167050e-14 
    -----------------------------------------------------------
    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