43-Tc-97



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      9/2+                  
       9.65000E+01       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)
     96.906366706 ± 0.000004045 (amu)  [mass excess = -87218.851 ± 3.769 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1099.548 ± 4.652 (keV) 
Strong Gamma-rays from Decay of Tc- 97 (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 
  ----------------------------------------------------------
         96.5             0.32         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 
       EC           4.21E+6 Y 16     
       EC           91.0 D 6         
       IT           91.0 D 6         
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Tc- 99 (Z= 43, A= 99), MT= 17 (n,3n)
     Ru- 98 (Z= 44, A= 98), MT= 28 (n,np)
     Ru- 98 (Z= 44, A= 98), MT=104 (n,d)
     Ru- 99 (Z= 44, A= 99), MT= 32 (n,nd)
     Ru- 99 (Z= 44, A= 99), 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)
    -----------------------------------------------------------
     Tc- 97    U-235   Thermal   1.426850e-13   9.131820e-14 
     Tc- 97    U-235   Fast      5.048130e-14   3.230800e-14 
     Tc- 97    U-235   High      2.009630e-09   1.286170e-09 
     Tc- 97    U-238   High      2.195760e-12   1.405280e-12 
     Tc- 97   Pu-239   Thermal   6.673590e-11   4.271100e-11 
     Tc- 97   Pu-239   Fast      3.693480e-11   2.363840e-11 
     Tc- 97   Pu-239   High      2.950070e-08   1.888050e-08 
     Tc- 97   Pu-241   Thermal   2.265850e-13   1.450140e-13 
     Tc- 97   Pu-241   Fast      1.538040e-13   9.843480e-14 
    -----------------------------------------------------------
     Tc- 97m   U-235   Thermal   3.303540e-14   2.114260e-14 
     Tc- 97m   U-235   Fast      1.019330e-14   6.523740e-15 
     Tc- 97m   U-235   High      2.534670e-10   1.622190e-10 
     Tc- 97m   U-238   High      2.769430e-13   1.772430e-13 
     Tc- 97m  Pu-239   Thermal   1.545120e-11   9.888760e-12 
     Tc- 97m  Pu-239   Fast      7.457990e-12   4.773130e-12 
     Tc- 97m  Pu-239   High      3.720810e-09   2.381320e-09 
     Tc- 97m  Pu-241   Thermal   5.246050e-14   3.357470e-14 
     Tc- 97m  Pu-241   Fast      3.105660e-14   1.987630e-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)
    -----------------------------------------------------------
     Tc- 97    U-235   Thermal   1.757200e-13   1.124610e-13 
     Tc- 97    U-235   Fast      6.067470e-14   3.883180e-14 
     Tc- 97    U-235   High      2.263100e-09   1.448390e-09 
     Tc- 97    U-238   High      2.472700e-12   1.582530e-12 
     Tc- 97   Pu-239   Thermal   8.218710e-11   5.259980e-11 
     Tc- 97   Pu-239   Fast      4.439280e-11   2.841140e-11 
     Tc- 97   Pu-239   High      3.322150e-08   2.126180e-08 
     Tc- 97   Pu-241   Thermal   2.790450e-13   1.785890e-13 
     Tc- 97   Pu-241   Fast      1.848610e-13   1.183110e-13 
    -----------------------------------------------------------
     Tc- 97m   U-235   Thermal   3.303540e-14   2.114260e-14 
     Tc- 97m   U-235   Fast      1.019330e-14   6.523740e-15 
     Tc- 97m   U-235   High      2.534670e-10   1.619790e-10 
     Tc- 97m   U-238   High      2.769430e-13   1.770510e-13 
     Tc- 97m  Pu-239   Thermal   1.545120e-11   9.888760e-12 
     Tc- 97m  Pu-239   Fast      7.457990e-12   4.773130e-12 
     Tc- 97m  Pu-239   High      3.720810e-09   2.379780e-09 
     Tc- 97m  Pu-241   Thermal   5.246050e-14   3.356920e-14 
     Tc- 97m  Pu-241   Fast      3.105660e-14   1.987630e-14 
    -----------------------------------------------------------
    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