Level energy(keV)   Spin & Parity       
       ground state      1+                    
       ground state(+X)  (4,5)                 
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)
     101.909209733 ± 0.000009866 (amu)  [mass excess = -84570.589 ± 9.191 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     4532.311 ± 9.170 (keV) 
Strong Gamma-rays from Decay of Tc-102 (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 
        468.9             0.88         B- 
        475.0             6.7          B- 
        865.5             0.87         B- 
        475.2            87.           B- 
        628.1            26.71         B- 
        630.2            16.09         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-           4.35 M 7         
       B-           5.28 S 15        
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Ru-102 (Z= 44, A=102), MT=103 (n,p)
     Ru-103 (Z= 44, A=103), MT= 28 (n,np)
     Ru-103 (Z= 44, A=103), MT=104 (n,d)
     Ru-104 (Z= 44, A=104), MT=105 (n,t)
     Rh-105 (Z= 45, A=105), MT=107 (n,α)

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)
     Tc-102    U-235   Thermal   3.663280e-05   2.344500e-05 
     Tc-102    U-235   Fast      1.665520e-06   1.065930e-06 
     Tc-102    U-235   High      3.737730e-05   2.392140e-05 
     Tc-102    U-238   Fast      2.353840e-07   1.506460e-07 
     Tc-102    U-238   High      2.110880e-06   1.350960e-06 
     Tc-102   Pu-239   Thermal   1.292260e-04   8.270510e-05 
     Tc-102   Pu-239   Fast      5.366130e-05   3.434310e-05 
     Tc-102   Pu-239   High      2.172210e-04   1.390210e-04 
     Tc-102   Pu-241   Thermal   5.703320e-06   3.650120e-06 
     Tc-102   Pu-241   Fast      4.630620e-06   2.963600e-06 
     Tc-102m   U-235   Thermal   1.541630e-04   9.866460e-05 
     Tc-102m   U-235   Fast      8.074370e-06   5.167590e-06 
     Tc-102m   U-235   High      2.933950e-04   1.877730e-04 
     Tc-102m   U-238   Fast      1.141130e-06   7.303230e-07 
     Tc-102m   U-238   High      1.656950e-05   1.060450e-05 
     Tc-102m  Pu-239   Thermal   5.438280e-04   3.480500e-04 
     Tc-102m  Pu-239   Fast      2.601470e-04   1.664940e-04 
     Tc-102m  Pu-239   High      1.705090e-03   1.091250e-03 
     Tc-102m  Pu-241   Thermal   2.400150e-05   1.536090e-05 
     Tc-102m  Pu-241   Fast      2.244900e-05   1.436740e-05 
    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)
     Tc-102    U-235   Thermal   4.261170e-02   6.817880e-03 
     Tc-102    U-235   Fast      4.347500e-02   8.695000e-04 
     Tc-102    U-235   High      3.228790e-02   7.426220e-03 
     Tc-102    U-238   Fast      6.442650e-02   1.288530e-03 
     Tc-102    U-238   High      4.621390e-02   5.083530e-03 
     Tc-102   Pu-239   Thermal   6.071710e-02   1.396490e-02 
     Tc-102   Pu-239   Fast      6.704410e-02   4.022650e-03 
     Tc-102   Pu-239   High      5.309820e-02   1.699140e-02 
     Tc-102   Pu-241   Thermal   6.650910e-02   2.660360e-03 
     Tc-102   Pu-241   Fast      6.854760e-02   1.919330e-03 
     Tc-102m   U-235   Thermal   1.541630e-04   1.695800e-05 
     Tc-102m   U-235   Fast      8.074370e-06   1.614870e-07 
     Tc-102m   U-235   High      2.933950e-04   4.694330e-05 
     Tc-102m   U-238   Fast      1.141130e-06   2.282260e-08 
     Tc-102m   U-238   High      1.656950e-05   1.822640e-06 
     Tc-102m  Pu-239   Thermal   5.438280e-04   1.250800e-04 
     Tc-102m  Pu-239   Fast      2.601470e-04   5.202950e-06 
     Tc-102m  Pu-239   High      1.705090e-03   2.728140e-04 
     Tc-102m  Pu-241   Thermal   2.400150e-05   9.600600e-07 
     Tc-102m  Pu-241   Fast      2.244900e-05   6.285730e-07 
    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