35-Br-82



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      5-                    
       4.59492E+01       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)
     81.916803246 ± 0.000001370 (amu)  [mass excess = -77497.277 ± 1.277 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     3093.041 ± 0.973 (keV) 
Strong Gamma-rays from Decay of Br- 82 (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 
  ----------------------------------------------------------
        698.37            0.03         B- 
        776.52            0.26         B- 
       1474.88            0.02         B- 
         45.95            --           IT 
  ----------------------------------------------------------
        554.35           71.06         B- 
        619.11           43.53         B- 
        776.52           83.4          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-           35.282 H 7       
       B-           6.13 M 5         
       IT           6.13 M 5         
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Br- 81 (Z= 35, A= 81), MT=102 (n,γ)
     Kr- 82 (Z= 36, A= 82), MT=103 (n,p)
     Kr- 83 (Z= 36, A= 83), MT= 28 (n,np)
     Kr- 83 (Z= 36, A= 83), MT=104 (n,d)
     Kr- 84 (Z= 36, A= 84), MT=105 (n,t)
     Rb- 85 (Z= 37, A= 85), MT=107 (n,α)
     Rb- 86 (Z= 37, A= 86), 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)
    -----------------------------------------------------------
     Br- 82    U-235   Thermal   3.821370e-07   2.445680e-07 
     Br- 82    U-235   Fast      1.040950e-06   6.662090e-07 
     Br- 82    U-235   High      3.808660e-05   2.285190e-06 
     Br- 82    U-238   Fast      8.970350e-08   5.741020e-08 
     Br- 82    U-238   High      1.419230e-06   9.083100e-07 
     Br- 82   Pu-239   Thermal   8.999420e-06   5.759630e-06 
     Br- 82   Pu-239   Fast      8.248310e-06   5.278920e-06 
     Br- 82   Pu-239   High      3.557590e-05   2.276860e-05 
     Br- 82   Pu-241   Thermal   2.263190e-06   1.448440e-06 
     Br- 82   Pu-241   Fast      7.394960e-07   4.732770e-07 
    -----------------------------------------------------------
     Br- 82m   U-235   Thermal   1.629940e-07   1.043170e-07 
     Br- 82m   U-235   Fast      3.811130e-07   2.439120e-07 
     Br- 82m   U-235   High      8.417180e-06   5.050310e-07 
     Br- 82m   U-238   Fast      3.284220e-08   2.101900e-08 
     Br- 82m   U-238   High      3.136520e-07   2.007380e-07 
     Br- 82m  Pu-239   Thermal   3.838550e-06   2.456680e-06 
     Br- 82m  Pu-239   Fast      3.019870e-06   1.932720e-06 
     Br- 82m  Pu-239   High      7.862310e-06   5.031880e-06 
     Br- 82m  Pu-241   Thermal   9.653280e-07   6.178110e-07 
     Br- 82m  Pu-241   Fast      2.707440e-07   1.732760e-07 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Br- 82    U-235   Thermal   5.412200e-07   3.463800e-07 
     Br- 82    U-235   Fast      1.412920e-06   9.042650e-07 
     Br- 82    U-235   High      4.630170e-05   1.851230e-06 
     Br- 82    U-238   Fast      1.217570e-07   7.792470e-08 
     Br- 82    U-238   High      1.725360e-06   1.104220e-06 
     Br- 82   Pu-239   Thermal   1.274590e-05   5.106420e-07 
     Br- 82   Pu-239   Fast      1.119570e-05   7.165250e-06 
     Br- 82   Pu-239   High      4.324950e-05   2.763070e-05 
     Br- 82   Pu-241   Thermal   3.205350e-06   2.049810e-06 
     Br- 82   Pu-241   Fast      1.003740e-06   6.413150e-07 
    -----------------------------------------------------------
     Br- 82m   U-235   Thermal   1.629940e-07   1.043170e-07 
     Br- 82m   U-235   Fast      3.811130e-07   2.439120e-07 
     Br- 82m   U-235   High      8.417180e-06   5.044360e-07 
     Br- 82m   U-238   Fast      3.284220e-08   2.101130e-08 
     Br- 82m   U-238   High      3.136520e-07   2.005200e-07 
     Br- 82m  Pu-239   Thermal   3.838550e-06   2.456680e-06 
     Br- 82m  Pu-239   Fast      3.019870e-06   1.932720e-06 
     Br- 82m  Pu-239   High      7.862310e-06   5.028620e-06 
     Br- 82m  Pu-241   Thermal   9.653280e-07   6.177110e-07 
     Br- 82m  Pu-241   Fast      2.707440e-07   1.732760e-07 
    -----------------------------------------------------------
    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