53-I-135



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)
     134.910048847 ± 0.000005798 (amu)  [mass excess = -83788.959 ± 5.402 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     2627.807 ± 4.990 (keV) 
Strong Gamma-rays from Decay of I-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 
  ----------------------------------------------------------
       1131.51           22.59         B- 
       1260.41           28.7          B- 
       1678.03            9.56         B- 
  ----------------------------------------------------------
       1131.51           22.59         B- 
       1260.41           28.7          B- 
       1678.03            9.56         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-           6.57 H 2         
       B-           6.58 H 3         
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, I-135.
     Figures of cross sections, I-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
     I -135 (Z= 53, A=135), MT=  2 (Elastic scattering)
     I -135 (Z= 53, A=135), MT=  4 (Inelastic scattering)
     Xe-135 (Z= 54, A=135), MT=103 (n,p)
     Xe-136 (Z= 54, A=136), MT= 28 (n,np)
     Xe-136 (Z= 54, A=136), MT=104 (n,d)
     Cs-136 (Z= 55, A=136), MT=111 (n,2p)
     Cs-137 (Z= 55, A=137), MT= 44 (n,n2p)
     Cs-137 (Z= 55, A=137), MT=106 (n,3He)
     Cs-137 (Z= 55, A=137), MT=115 (n,pd)

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)
    -----------------------------------------------------------
      I-135    U-235   Thermal   2.922920e-02   8.184180e-04 
      I-135    U-235   Fast      3.595840e-02   2.876670e-03 
      I-135    U-235   High      3.138840e-02   5.022140e-03 
      I-135    U-238   Fast      1.355070e-02   4.336230e-03 
      I-135    U-238   High      2.571660e-02   5.914820e-03 
      I-135   Pu-239   Thermal   4.286800e-02   2.572080e-03 
      I-135   Pu-239   Fast      3.921340e-02   4.313480e-03 
      I-135   Pu-239   High      3.231430e-02   1.034060e-02 
      I-135   Pu-241   Thermal   3.009190e-02   6.921120e-03 
      I-135   Pu-241   Fast      2.847460e-02   9.111850e-03 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
      I-135    U-235   Thermal   6.266820e-02   8.922490e-04 
      I-135    U-235   Fast      6.274390e-02   2.527510e-03 
      I-135    U-235   High      4.222870e-02   3.374960e-03 
      I-135    U-238   Fast      6.895930e-02   1.069960e-03 
      I-135    U-238   High      5.497090e-02   1.103260e-03 
      I-135   Pu-239   Thermal   6.538580e-02   1.832030e-03 
      I-135   Pu-239   Fast      6.078620e-02   2.432810e-03 
      I-135   Pu-239   High      3.958250e-02   1.780450e-02 
      I-135   Pu-241   Thermal   6.935410e-02   1.945610e-03 
      I-135   Pu-241   Fast      6.802740e-02   7.500520e-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