55-Cs-137



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      7/2+                  
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)
     136.907089231 ± 0.000000355 (amu)  [mass excess = -86545.824 ± 0.331 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     1175.629 ± 0.172 (keV) 
Strong Gamma-rays from Decay of Cs-137 (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 
  ----------------------------------------------------------
        283.5           6.E-04         B- 
        661.66           85.1          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-           30.08 Y 9        
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Cs-137.
     Figures of cross sections, Cs-137:  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-136 (Z= 55, A=136), MT=102 (n,γ)
     Cs-137 (Z= 55, A=137), MT=  2 (Elastic scattering)
     Cs-137 (Z= 55, A=137), MT=  4 (Inelastic scattering)
     Ba-137 (Z= 56, A=137), MT=103 (n,p)
     Ba-138 (Z= 56, A=138), MT= 28 (n,np)
     Ba-138 (Z= 56, A=138), MT=104 (n,d)
     Ba-140 (Z= 56, A=140), MT= 33 (n,nt)
     La-139 (Z= 57, A=139), MT=106 (n,3He)
     La-140 (Z= 57, A=140), 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)
    -----------------------------------------------------------
     Cs-137    U-235   Thermal   5.990760e-04   6.589830e-05 
     Cs-137    U-235   Fast      2.278840e-03   7.292270e-04 
     Cs-137    U-235   High      9.489290e-03   3.036580e-03 
     Cs-137    U-238   Fast      1.121620e-04   7.178360e-05 
     Cs-137    U-238   High      4.216020e-03   1.897210e-03 
     Cs-137   Pu-239   Thermal   5.972290e-03   9.555660e-04 
     Cs-137   Pu-239   Fast      1.004280e-02   1.606860e-03 
     Cs-137   Pu-239   High      1.613370e-02   3.710740e-03 
     Cs-137   Pu-241   Thermal   9.238090e-04   5.912380e-04 
     Cs-137   Pu-241   Fast      8.695460e-04   5.565100e-04 
    -----------------------------------------------------------
    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-137    U-235   Thermal   6.175280e-02   3.357540e-04 
     Cs-137    U-235   Fast      6.206820e-02   3.436130e-04 
     Cs-137    U-235   High      4.932800e-02   2.956630e-03 
     Cs-137    U-238   Fast      6.050970e-02   6.054580e-04 
     Cs-137    U-238   High      5.150220e-02   1.441500e-03 
     Cs-137   Pu-239   Thermal   6.604780e-02   3.313970e-04 
     Cs-137   Pu-239   Fast      6.582260e-02   4.615150e-04 
     Cs-137   Pu-239   High      4.454610e-02   3.562060e-03 
     Cs-137   Pu-241   Thermal   6.648990e-02   4.658530e-04 
     Cs-137   Pu-241   Fast      6.378670e-02   3.832770e-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