60-Nd-150



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)
     149.920902249 ± 0.000001821 (amu)  [mass excess = -73679.080 ± 1.696 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -82.616 ± 20.001 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Nd-150.
     Figures of cross sections, Nd-150:  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-150 (Z= 60, A=150), MT=  2 (Elastic scattering)
     Nd-150 (Z= 60, A=150), MT=  4 (Inelastic scattering)
     Pm-151 (Z= 61, A=151), MT= 28 (n,np)
     Pm-151 (Z= 61, A=151), MT=104 (n,d)
     Sm-152 (Z= 62, A=152), MT=106 (n,3He)
     Sm-153 (Z= 62, A=153), MT=107 (n,α)
     Sm-154 (Z= 62, A=154), 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)
    -----------------------------------------------------------
     Nd-150    U-235   Thermal   3.267300e-04   2.091070e-04 
     Nd-150    U-235   Fast      2.015740e-04   1.290070e-04 
     Nd-150    U-235   High      1.200890e-03   7.685730e-04 
     Nd-150    U-238   Fast      4.262590e-05   2.728060e-05 
     Nd-150    U-238   High      2.707650e-04   1.732900e-04 
     Nd-150   Pu-239   Thermal   1.736790e-03   1.111540e-03 
     Nd-150   Pu-239   Fast      1.912870e-03   1.224230e-03 
     Nd-150   Pu-239   High      4.073220e-03   2.606860e-03 
     Nd-150   Pu-241   Thermal   2.550310e-04   1.632190e-04 
     Nd-150   Pu-241   Fast      4.510510e-04   2.886730e-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)
    -----------------------------------------------------------
     Nd-150    U-235   Thermal   6.523220e-03   3.395100e-05 
     Nd-150    U-235   Fast      6.845320e-03   3.657630e-05 
     Nd-150    U-235   High      5.116600e-03   5.620210e-04 
     Nd-150    U-238   Fast      1.276260e-02   1.303820e-04 
     Nd-150    U-238   High      1.082940e-02   1.729540e-03 
     Nd-150   Pu-239   Thermal   9.661870e-03   3.383760e-05 
     Nd-150   Pu-239   Fast      9.945130e-03   4.974480e-05 
     Nd-150   Pu-239   High      9.392610e-03   1.501840e-03 
     Nd-150   Pu-241   Thermal   1.210000e-02   1.210940e-04 
     Nd-150   Pu-241   Fast      1.229620e-02   1.231980e-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