49-In-113



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      9/2+                  
       3.91691E+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)
     112.904061839 ± 0.000000914 (amu)  [mass excess = -89365.821 ± 0.852 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1037.581 ± 1.696 (keV) 
Strong Gamma-rays from Decay of In-113 (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 
  ----------------------------------------------------------
        391.70           64.94         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 
       IT           1.6579 H 4       
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, In-113.
     Figures of cross sections, In-113:  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-113 (Z= 49, A=113), MT=  2 (Elastic scattering)
     In-113 (Z= 49, A=113), MT=  4 (Inelastic scattering)
     In-115 (Z= 49, A=115), MT= 17 (n,3n)
     Sn-114 (Z= 50, A=114), MT= 28 (n,np)
     Sn-114 (Z= 50, A=114), MT=104 (n,d)
     Sn-115 (Z= 50, A=115), MT= 32 (n,nd)
     Sn-115 (Z= 50, A=115), MT= 41 (n,2np)
     Sn-115 (Z= 50, A=115), 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-113    U-235   High      2.857060e-11   1.828520e-11 
     In-113    U-238   High      4.684860e-14   2.998310e-14 
     In-113   Pu-239   High      1.128490e-08   7.222350e-09 
    -----------------------------------------------------------
     In-113m   U-235   High      3.603500e-12   2.306240e-12 
     In-113m  Pu-239   High      1.423320e-09   9.109270e-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)
    -----------------------------------------------------------
     In-113    U-235   Thermal   1.418260e-04   2.141750e-07 
     In-113    U-235   Fast      3.254740e-04   6.633350e-07 
     In-113    U-235   High      1.092900e-02   8.731780e-04 
     In-113    U-238   Fast      4.612930e-04   1.804150e-07 
     In-113    U-238   High      9.153340e-03   5.486940e-04 
     In-113   Pu-239   Thermal   8.165080e-04   1.216540e-07 
     In-113   Pu-239   Fast      1.276410e-03   1.864970e-07 
     In-113   Pu-239   High      1.296110e-02   1.424810e-03 
     In-113   Pu-241   Thermal   1.519490e-03   2.452870e-07 
     In-113   Pu-241   Fast      2.130800e-03   1.612350e-06 
    -----------------------------------------------------------
     In-113m   U-235   High      3.603500e-12   2.302820e-12 
     In-113m  Pu-239   High      1.425550e-09   9.103420e-10 
    -----------------------------------------------------------
    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