50-Sn-115



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      1/2+                  
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)
     114.903344699 ± 0.000000016 (amu)  [mass excess = -90033.833 ± 0.015 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -3030.430 ± 16.025 (keV) 
Strong Gamma-rays from Decay of Sn-115 (Compiled from ENSDF as of March 2011)
  [ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
   γ-ray energy(keV)  Intensity(%)  Decay mode 
  ----------------------------------------------------------
        100.7            14.84         IT 
        115.9            53.           IT 
        497.6         ~  84.8          IT 
  ----------------------------------------------------------
     *: relative, ~ approximate, ? calculated or estimatted 
     >: greater than or equal to, <: less than or equal to  
  [ Intensities; total intensity of the nuclide is 100(%). ]
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Sn-115.
     Figures of cross sections, Sn-115:  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=102 (n,γ)
     Sn-115 (Z= 50, A=115), MT=  2 (Elastic scattering)
     Sn-115 (Z= 50, A=115), MT=  4 (Inelastic scattering)
     Sn-116 (Z= 50, A=116), MT= 16 (n,2n)
     Sn-117 (Z= 50, A=117), 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-115    U-235   High      1.602200e-12   1.025400e-12 
     Sn-115   Pu-239   High      1.010660e-09   6.468190e-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)
    -----------------------------------------------------------
     Sn-115    U-235   Thermal   1.256070e-04   2.235610e-07 
     Sn-115    U-235   Fast      3.379690e-04   8.084460e-07 
     Sn-115    U-235   High      1.093330e-02   3.061570e-04 
     Sn-115    U-238   Fast      3.757070e-04   2.245360e-07 
     Sn-115    U-238   High      8.578670e-03   8.192840e-06 
     Sn-115   Pu-239   Thermal   4.258020e-04   1.925510e-07 
     Sn-115   Pu-239   Fast      8.136190e-04   4.573380e-07 
     Sn-115   Pu-239   High      1.272400e-02   7.630650e-04 
     Sn-115   Pu-241   Thermal   3.807720e-04   9.767250e-08 
     Sn-115   Pu-241   Fast      1.089000e-03   1.200940e-06 
    -----------------------------------------------------------
    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