Level energy(keV)   Spin & Parity       
       ground state      9/2+                  
       3.36244E+02       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)
     114.903878776 ± 0.000000012 (amu)  [mass excess = -89536.343 ± 0.012 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     497.490 ± 0.010 (keV) 
Strong Gamma-rays from Decay of In-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 
        497.37            0.05         B- 
        336.24           45.79         IT 
     *: relative, ~ approximate, ? calculated or estimatted 
     >: greater than or equal to, <: less than or equal to  
  [ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
     Decay mode     Half-life 
       B-           4.41E+14 Y 25    
       B-           4.486 H 4        
       IT           4.486 H 4        
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, In-115.
     Figures of cross sections, In-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
     In-115 (Z= 49, A=115), MT=  2 (Elastic scattering)
     In-115 (Z= 49, A=115), MT=  4 (Inelastic scattering)
     Sn-115 (Z= 50, A=115), MT=103 (n,p)
     Sn-116 (Z= 50, A=116), MT= 28 (n,np)
     Sn-116 (Z= 50, A=116), MT=104 (n,d)
     Sn-117 (Z= 50, A=117), MT= 32 (n,nd)
     Sn-117 (Z= 50, A=117), MT= 41 (n,2np)
     Sn-117 (Z= 50, A=117), MT=105 (n,t)

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)
     In-115    U-235   Thermal   1.631140e-12   1.043940e-12 
     In-115    U-235   Fast      1.820810e-12   1.165320e-12 
     In-115    U-235   High      1.008380e-08   6.453590e-09 
     In-115    U-238   Fast      9.654820e-15   6.179070e-15 
     In-115    U-238   High      9.191930e-11   5.882840e-11 
     In-115   Pu-239   Thermal   1.412660e-11   9.041010e-12 
     In-115   Pu-239   Fast      4.982870e-11   3.189030e-11 
     In-115   Pu-239   High      1.058290e-06   6.773080e-07 
     In-115   Pu-241   Fast      6.177120e-13   3.953350e-13 
     In-115m   U-235   Thermal   3.776540e-13   2.416990e-13 
     In-115m   U-235   Fast      3.676640e-13   2.353050e-13 
     In-115m   U-235   High      1.271830e-09   8.139700e-10 
     In-115m   U-238   High      1.159340e-11   7.419820e-12 
     In-115m  Pu-239   Thermal   3.270680e-12   2.093230e-12 
     In-115m  Pu-239   Fast      1.006160e-11   6.439420e-12 
     In-115m  Pu-239   High      1.334790e-07   8.542630e-08 
     In-115m  Pu-241   Fast      1.247300e-13   7.982730e-14 
    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)
     In-115    U-235   Thermal   1.196470e-04   5.221450e-06 
     In-115    U-235   Fast      3.219340e-04   1.413950e-05 
     In-115    U-235   High      1.057640e-02   3.165740e-04 
     In-115    U-238   Fast      3.578820e-04   8.726650e-06 
     In-115    U-238   High      8.171670e-03   3.483350e-04 
     In-115   Pu-239   Thermal   4.056010e-04   2.539500e-05 
     In-115   Pu-239   Fast      7.750200e-04   3.346470e-05 
     In-115   Pu-239   High      1.212640e-02   7.551620e-04 
     In-115   Pu-241   Thermal   3.627070e-04   5.242730e-06 
     In-115   Pu-241   Fast      1.037330e-03   1.169340e-04 
     In-115m   U-235   Thermal   1.192020e-04   7.743030e-06 
     In-115m   U-235   Fast      3.206930e-04   1.320000e-05 
     In-115m   U-235   High      7.137950e-03   8.230340e-04 
     In-115m   U-238   Fast      3.564950e-04   1.211270e-05 
     In-115m   U-238   High      8.140090e-03   4.202990e-04 
     In-115m  Pu-239   Thermal   4.040220e-04   2.692100e-05 
     In-115m  Pu-239   Fast      7.719640e-04   3.906010e-05 
     In-115m  Pu-239   High      1.195170e-02   1.002860e-03 
     In-115m  Pu-241   Thermal   3.613010e-04   1.197150e-05 
     In-115m  Pu-241   Fast      1.033330e-03   2.323980e-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