55-Cs-135



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      7/2+                  
       1.63330E+03       19/2-                 
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)
     134.905977049 ± 0.000001069 (amu)  [mass excess = -87581.815 ± 0.996 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     268.898 ± 1.033 (keV) 
Strong Gamma-rays from Decay of Cs-135 (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 
  ----------------------------------------------------------
        787.2            99.7          IT 
        846.1            96.           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 
       B-           2.3E+6 Y 3       
       IT           53 M 2           
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Cs-135.
     Figures of cross sections, Cs-135:  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
     Cs-134 (Z= 55, A=134), MT=102 (n,γ)
     Cs-135 (Z= 55, A=135), MT=  2 (Elastic scattering)
     Cs-135 (Z= 55, A=135), MT=  4 (Inelastic scattering)
     Cs-136 (Z= 55, A=136), MT= 16 (n,2n)
     Cs-137 (Z= 55, A=137), MT= 17 (n,3n)
     Ba-135 (Z= 56, A=135), MT=103 (n,p)
     Ba-136 (Z= 56, A=136), MT= 28 (n,np)
     Ba-136 (Z= 56, A=136), MT=104 (n,d)
     Ba-137 (Z= 56, A=137), MT= 32 (n,nd)
     Ba-137 (Z= 56, A=137), MT=105 (n,t)
     La-138 (Z= 57, A=138), MT=107 (n,α)
     La-139 (Z= 57, A=139), 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)
    -----------------------------------------------------------
     Cs-135    U-235   Thermal   3.044270e-06   1.948330e-06 
     Cs-135    U-235   Fast      1.182060e-06   7.565180e-07 
     Cs-135    U-235   High      2.570380e-04   1.645040e-04 
     Cs-135    U-238   Fast      2.134040e-07   1.365790e-07 
     Cs-135    U-238   High      1.134170e-05   7.258650e-06 
     Cs-135   Pu-239   Thermal   7.825850e-05   5.008540e-05 
     Cs-135   Pu-239   Fast      7.197260e-05   4.606250e-05 
     Cs-135   Pu-239   High      8.165510e-04   5.225930e-04 
     Cs-135   Pu-241   Thermal   4.540250e-06   2.905760e-06 
     Cs-135   Pu-241   Fast      4.309260e-06   2.757930e-06 
    -----------------------------------------------------------
     Cs-135m   U-235   Thermal   1.857930e-06   1.189080e-06 
     Cs-135m   U-235   Fast      8.736950e-07   5.591650e-07 
     Cs-135m   U-235   High      3.491840e-04   2.234770e-04 
     Cs-135m   U-238   Fast      1.577340e-07   1.009500e-07 
     Cs-135m   U-238   High      1.540750e-05   9.860800e-06 
     Cs-135m  Pu-239   Thermal   4.776160e-05   3.056740e-05 
     Cs-135m  Pu-239   Fast      5.319710e-05   3.404620e-05 
     Cs-135m  Pu-239   High      1.109280e-03   7.099380e-04 
     Cs-135m  Pu-241   Thermal   2.770940e-06   1.773400e-06 
     Cs-135m  Pu-241   Fast      3.185100e-06   2.038470e-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)
    -----------------------------------------------------------
     Cs-135    U-235   Thermal   6.523550e-02   2.764030e-04 
     Cs-135    U-235   Fast      6.579160e-02   5.124000e-04 
     Cs-135    U-235   High      5.735610e-02   3.436420e-03 
     Cs-135    U-238   Fast      6.922840e-02   6.621410e-04 
     Cs-135    U-238   High      5.835060e-02   1.170260e-03 
     Cs-135   Pu-239   Thermal   7.617440e-02   5.358810e-04 
     Cs-135   Pu-239   Fast      7.551260e-02   3.800030e-04 
     Cs-135   Pu-239   High      6.377160e-02   6.997480e-03 
     Cs-135   Pu-241   Thermal   7.163080e-02   7.212910e-04 
     Cs-135   Pu-241   Fast      7.054840e-02   1.421740e-03 
    -----------------------------------------------------------
     Cs-135m   U-235   Thermal   1.857930e-06   1.189080e-06 
     Cs-135m   U-235   Fast      8.736950e-07   5.591650e-07 
     Cs-135m   U-235   High      3.491840e-04   2.231460e-04 
     Cs-135m   U-238   Fast      1.577340e-07   1.009130e-07 
     Cs-135m   U-238   High      1.540750e-05   9.850120e-06 
     Cs-135m  Pu-239   Thermal   4.776160e-05   3.056740e-05 
     Cs-135m  Pu-239   Fast      5.319710e-05   3.404620e-05 
     Cs-135m  Pu-239   High      1.109280e-03   7.094780e-04 
     Cs-135m  Pu-241   Thermal   2.770940e-06   1.773110e-06 
     Cs-135m  Pu-241   Fast      3.185100e-06   2.038470e-06 
    -----------------------------------------------------------
    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