Level energy(keV)   Spin & Parity       
       ground state      9/2+                  
       1.42683E+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)
     98.906250844 ± 0.000001037 (amu)  [mass excess = -87326.776 ± 0.966 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     295.062 ± 1.133 (keV) 
Strong Gamma-rays from Decay of Tc- 99 (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 
         89.5           7.E-04         B- 
          2.17            --           IT 
        140.51           89.           IT 
        142.63            0.02         IT 
         89.6             --           B- 
        232.8           9.E-06         B- 
        322.4           1.E-04         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-           6.0067 H 5       
       B-           2.111E+5 Y 12    
       IT           6.0067 H 5       
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Tc-99.
     Figures of cross sections, Tc-99:  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
     Tc- 99 (Z= 43, A= 99), MT=  2 (Elastic scattering)
     Tc- 99 (Z= 43, A= 99), MT=  4 (Inelastic scattering)
     Ru- 99 (Z= 44, A= 99), MT=103 (n,p)
     Ru-100 (Z= 44, A=100), MT= 28 (n,np)
     Ru-100 (Z= 44, A=100), MT=104 (n,d)
     Ru-101 (Z= 44, A=101), MT= 32 (n,nd)
     Ru-101 (Z= 44, A=101), MT=105 (n,t)
     Rh-103 (Z= 45, A=103), 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)
     Tc- 99    U-235   Thermal   1.231460e-09   7.881390e-10 
     Tc- 99    U-235   Fast      4.852190e-10   3.105400e-10 
     Tc- 99    U-235   High      8.145250e-07   5.212960e-07 
     Tc- 99    U-238   Fast      1.995050e-11   1.276830e-11 
     Tc- 99    U-238   High      5.114230e-09   3.273110e-09 
     Tc- 99   Pu-239   Thermal   1.202390e-07   7.695250e-08 
     Tc- 99   Pu-239   Fast      7.278820e-08   4.658450e-08 
     Tc- 99   Pu-239   High      6.410190e-06   4.102520e-06 
     Tc- 99   Pu-241   Thermal   1.613710e-09   1.032770e-09 
     Tc- 99   Pu-241   Fast      1.030900e-09   6.597790e-10 
     Tc- 99m   U-235   Thermal   2.851170e-10   1.824750e-10 
     Tc- 99m   U-235   Fast      9.797700e-11   6.270520e-11 
     Tc- 99m   U-235   High      1.027330e-07   6.574880e-08 
     Tc- 99m   U-238   Fast      4.028460e-12   2.578210e-12 
     Tc- 99m   U-238   High      6.450380e-10   4.128250e-10 
     Tc- 99m  Pu-239   Thermal   2.783850e-08   1.781660e-08 
     Tc- 99m  Pu-239   Fast      1.469760e-08   9.406490e-09 
     Tc- 99m  Pu-239   High      8.084920e-07   5.174350e-07 
     Tc- 99m  Pu-241   Thermal   3.736170e-10   2.391150e-10 
     Tc- 99m  Pu-241   Fast      2.081630e-10   1.332250e-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)
     Tc- 99    U-235   Thermal   6.138470e-02   6.794330e-04 
     Tc- 99    U-235   Fast      5.977410e-02   6.861130e-04 
     Tc- 99    U-235   High      5.163510e-02   1.464660e-03 
     Tc- 99    U-238   Fast      6.258370e-02   1.248160e-03 
     Tc- 99    U-238   High      5.766420e-02   8.353120e-04 
     Tc- 99   Pu-239   Thermal   6.232680e-02   8.945320e-04 
     Tc- 99   Pu-239   Fast      6.002800e-02   1.213570e-03 
     Tc- 99   Pu-239   High      4.766000e-02   1.906830e-03 
     Tc- 99   Pu-241   Thermal   6.002950e-02   1.261260e-03 
     Tc- 99   Pu-241   Fast      5.569900e-02   3.342530e-03 
     Tc- 99m   U-235   Thermal   5.340660e-02   8.301400e-04 
     Tc- 99m   U-235   Fast      5.200530e-02   7.891200e-04 
     Tc- 99m   U-235   High      4.492340e-02   1.293900e-03 
     Tc- 99m   U-238   Fast      5.444970e-02   7.785210e-04 
     Tc- 99m   U-238   High      5.016960e-02   7.039320e-04 
     Tc- 99m  Pu-239   Thermal   5.422610e-02   8.812300e-04 
     Tc- 99m  Pu-239   Fast      5.222620e-02   1.133580e-03 
     Tc- 99m  Pu-239   High      4.146010e-02   1.704340e-03 
     Tc- 99m  Pu-241   Thermal   5.222750e-02   1.075620e-03 
     Tc- 99m  Pu-241   Fast      4.845980e-02   2.925840e-03 
    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