Level energy(keV)   Spin & Parity       
       ground state      1+                    
       7.00000E+01       (5)+                  
       ground state(+X)  (8-)                  
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)
     119.907966567 ± 0.000042952 (amu)  [mass excess = -85728.591 ± 40.010 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     5370.000 ± 40.000 (keV) 
Strong Gamma-rays from Decay of In-120 (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 
        197.36           81.           B- 
       1023.02           99.           B- 
       1171.22          100.           B- 
        704.2             1.43         B- 
       1172.5            19.           B- 
       2039.8             1.86         B- 
        863.64           35.02         B- 
       1023.02           56.26         B- 
       1171.22           97.           B- 
     *: 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-           3.08 S 8         
       B-           46.2 S 8         
       B-           47.3 S 5         
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Sn-120 (Z= 50, A=120), MT=103 (n,p)
     Sn-122 (Z= 50, A=122), MT=105 (n,t)
     Sb-123 (Z= 51, A=123), MT=107 (n,α)
     Sb-124 (Z= 51, A=124), MT= 22 (n,nα)

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-120    U-235   Thermal   2.597760e-06   1.662570e-06 
     In-120    U-235   Fast      3.933840e-06   2.517650e-06 
     In-120    U-235   High      1.044940e-04   6.687640e-05 
     In-120    U-238   Fast      4.182880e-07   2.677040e-07 
     In-120    U-238   High      8.058460e-06   5.157440e-06 
     In-120   Pu-239   Thermal   1.326340e-05   8.488620e-06 
     In-120   Pu-239   Fast      2.279530e-05   1.458910e-05 
     In-120   Pu-239   High      4.886920e-04   3.127630e-04 
     In-120   Pu-241   Thermal   2.313180e-06   1.480440e-06 
     In-120   Pu-241   Fast      7.093190e-06   4.539640e-06 
     In-120m   U-235   Thermal   5.788880e-06   2.717450e-06 
     In-120m   U-235   Fast      1.009050e-05   4.774220e-06 
     In-120m   U-235   High      4.334440e-04   2.098010e-04 
     In-120m   U-238   Fast      1.072930e-06   5.076470e-07 
     In-120m   U-238   High      3.342650e-05   1.617970e-05 
     In-120m  Pu-239   Thermal   2.955640e-05   1.387450e-05 
     In-120m  Pu-239   Fast      5.847140e-05   2.766520e-05 
     In-120m  Pu-239   High      2.027100e-03   9.811860e-04 
     In-120m  Pu-241   Thermal   5.154710e-06   2.419750e-06 
     In-120m  Pu-241   Fast      1.819450e-05   8.608520e-06 
    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-120    U-235   Thermal   1.221910e-04   6.045610e-05 
     In-120    U-235   Fast      3.455570e-04   2.031630e-04 
     In-120    U-235   High      1.061910e-02   5.743100e-03 
     In-120    U-238   Fast      3.867360e-04   2.118720e-04 
     In-120    U-238   High      7.763600e-03   4.254590e-03 
     In-120   Pu-239   Thermal   2.862410e-04   1.644660e-04 
     In-120   Pu-239   Fast      5.171670e-04   2.971870e-04 
     In-120   Pu-239   High      1.101700e-02   5.320720e-03 
     In-120   Pu-241   Thermal   2.530130e-04   1.372450e-04 
     In-120   Pu-241   Fast      8.525690e-04   5.027040e-04 
     In-120m   U-235   Thermal   5.788880e-06   1.331440e-06 
     In-120m   U-235   Fast      1.009050e-05   6.457930e-06 
     In-120m   U-235   High      4.334440e-04   1.950500e-04 
     In-120m   U-238   Fast      1.072930e-06   4.828210e-07 
     In-120m   U-238   High      3.342650e-05   1.504200e-05 
     In-120m  Pu-239   Thermal   2.955640e-05   1.891610e-05 
     In-120m  Pu-239   Fast      5.847140e-05   3.742160e-05 
     In-120m  Pu-239   High      2.027100e-03   6.486720e-04 
     In-120m  Pu-241   Thermal   5.154710e-06   2.319620e-06 
     In-120m  Pu-241   Fast      1.819450e-05   1.164450e-05 
    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