35-Br-97



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state                            
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)
     96.963440 ± 0.000430 (amu)  [mass excess = -34055 ± 401 (keV) ]
 	[These values were derived from systematical trend]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     13368 ± 421 (keV) [derived from systematical trend] 
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0 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- 97    U-235   Thermal   3.431570e-12   2.196210e-12 
     Br- 97    U-235   Fast      1.725570e-11   1.104370e-11 
     Br- 97    U-235   High      4.504870e-10   2.883120e-10 
     Br- 97    U-238   Fast      7.212770e-09   4.616170e-09 
     Br- 97    U-238   High      3.024570e-09   1.935720e-09 
     Br- 97   Pu-239   Thermal   7.722100e-10   4.942140e-10 
     Br- 97   Pu-239   Fast      5.797710e-12   3.710530e-12 
     Br- 97   Pu-239   High      4.018520e-10   2.571850e-10 
     Br- 97   Pu-241   Thermal   1.309570e-11   8.381270e-12 
     Br- 97   Pu-241   Fast      3.670500e-11   2.349120e-11 
    -----------------------------------------------------------
    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- 97    U-235   Thermal   3.431570e-12   2.196210e-12 
     Br- 97    U-235   Fast      1.725570e-11   1.104370e-11 
     Br- 97    U-235   High      4.504870e-10   2.878850e-10 
     Br- 97    U-238   Fast      7.212770e-09   4.614720e-09 
     Br- 97    U-238   High      3.024570e-09   1.933620e-09 
     Br- 97   Pu-239   Thermal   7.722100e-10   4.942140e-10 
     Br- 97   Pu-239   Fast      5.797710e-12   3.710530e-12 
     Br- 97   Pu-239   High      4.018520e-10   2.570180e-10 
     Br- 97   Pu-241   Thermal   1.309570e-11   8.379910e-12 
     Br- 97   Pu-241   Fast      3.670500e-11   2.349120e-11 
    -----------------------------------------------------------
    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