50-Sn-114



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)
     113.902782695 ± 0.000001042 (amu)  [mass excess = -90557.336 ± 0.971 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -6061.691 ± 21.846 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Sn-114.
     Figures of cross sections, Sn-114:  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
     Sn-114 (Z= 50, A=114), MT=  2 (Elastic scattering)
     Sn-114 (Z= 50, A=114), MT=  4 (Inelastic scattering)
     Sn-115 (Z= 50, A=115), MT= 16 (n,2n)
     Sn-116 (Z= 50, A=116), MT= 17 (n,3n)

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)
    -----------------------------------------------------------
     Sn-114    U-235   High      4.976820e-14   3.185170e-14 
     Sn-114   Pu-239   High      5.553600e-11   3.554310e-11 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Sn-114    U-235   Fast      9.778480e-15   6.258200e-15 
     Sn-114    U-235   High      8.332530e-10   5.230760e-10 
     Sn-114    U-238   High      2.586080e-12   4.606670e-14 
     Sn-114   Pu-239   Thermal   7.211270e-14   1.213650e-15 
     Sn-114   Pu-239   Fast      2.635690e-13   4.573710e-15 
     Sn-114   Pu-239   High      1.332720e-07   8.326430e-08 
    -----------------------------------------------------------
    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