62-Sm-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)
     149.917282919 ± 0.000001809 (amu)  [mass excess = -77050.464 ± 1.685 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -2258.642 ± 6.190 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Sm-150.
     Figures of cross sections, Sm-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
     Sm-149 (Z= 62, A=149), MT=102 (n,γ)
     Sm-150 (Z= 62, A=150), MT=  2 (Elastic scattering)
     Sm-150 (Z= 62, A=150), MT=  4 (Inelastic scattering)
     Sm-151 (Z= 62, A=151), MT= 16 (n,2n)
     Sm-152 (Z= 62, A=152), MT= 17 (n,3n)
     Eu-151 (Z= 63, A=151), MT= 28 (n,np)
     Eu-151 (Z= 63, A=151), MT=104 (n,d)
     Eu-152 (Z= 63, A=152), MT= 32 (n,nd)
     Eu-152 (Z= 63, A=152), MT= 41 (n,2np)
     Eu-152 (Z= 63, A=152), MT=105 (n,t)
     Eu-153 (Z= 63, A=153), MT= 33 (n,nt)
     Gd-152 (Z= 64, A=152), MT=106 (n,3He)
     Gd-153 (Z= 64, A=153), MT=107 (n,α)
     Gd-154 (Z= 64, A=154), MT= 22 (n,nα)
     Gd-155 (Z= 64, A=155), 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)
    -----------------------------------------------------------
     Sm-150    U-235   Thermal   1.218060e-10   7.795590e-11 
     Sm-150    U-235   Fast      4.560580e-11   2.918770e-11 
     Sm-150    U-235   High      3.064200e-07   1.961090e-07 
     Sm-150    U-238   Fast      1.710640e-12   1.094810e-12 
     Sm-150    U-238   High      7.628300e-10   4.882120e-10 
     Sm-150   Pu-239   Thermal   2.539600e-08   1.625340e-08 
     Sm-150   Pu-239   Fast      3.239470e-08   2.073260e-08 
     Sm-150   Pu-239   High      9.586220e-06   6.135180e-06 
     Sm-150   Pu-241   Thermal   6.100990e-11   3.904630e-11 
     Sm-150   Pu-241   Fast      2.797900e-10   1.790650e-10 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Sm-150    U-235   Thermal   2.996450e-07   1.917720e-07 
     Sm-150    U-235   Fast      2.505290e-07   1.603390e-07 
     Sm-150    U-235   High      9.348950e-06   5.970550e-06 
     Sm-150    U-238   Fast      3.291400e-08   2.105610e-08 
     Sm-150    U-238   High      2.530370e-07   1.612840e-07 
     Sm-150   Pu-239   Thermal   1.152360e-05   7.372710e-06 
     Sm-150   Pu-239   Fast      2.227880e-05   1.425840e-05 
     Sm-150   Pu-239   High      5.515360e-04   3.527420e-04 
     Sm-150   Pu-241   Thermal   5.081430e-07   3.251200e-07 
     Sm-150   Pu-241   Fast      1.119440e-06   7.164400e-07 
    -----------------------------------------------------------
    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