63-Eu-157



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      5/2+                  
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)
     156.925433446 ± 0.000004639 (amu)  [mass excess = -69458.297 ± 4.322 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     1364.524 ± 4.218 (keV) 
Strong Gamma-rays from Decay of Eu-157 (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 
  ----------------------------------------------------------
         63.93           22.99         B- 
        370.51           11.           B- 
        410.72           17.49         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-           15.18 H 3        
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Eu-157.
     Figures of cross sections, Eu-157:  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
     Eu-156 (Z= 63, A=156), MT=102 (n,γ)
     Eu-157 (Z= 63, A=157), MT=  2 (Elastic scattering)
     Eu-157 (Z= 63, A=157), MT=  4 (Inelastic scattering)
     Gd-157 (Z= 64, A=157), MT=103 (n,p)
     Gd-158 (Z= 64, A=158), MT= 28 (n,np)
     Gd-158 (Z= 64, A=158), MT=104 (n,d)
     Gd-160 (Z= 64, A=160), MT= 33 (n,nt)
     Tb-159 (Z= 65, A=159), MT=106 (n,3He)
     Tb-160 (Z= 65, A=160), 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)
    -----------------------------------------------------------
     Eu-157    U-235   Thermal   6.339900e-07   4.057540e-07 
     Eu-157    U-235   Fast      4.730240e-07   3.027350e-07 
     Eu-157    U-235   High      6.134410e-05   3.926030e-05 
     Eu-157    U-238   Fast      1.960730e-07   1.254870e-07 
     Eu-157    U-238   High      5.425900e-06   3.472580e-06 
     Eu-157   Pu-239   Thermal   3.457460e-05   2.212770e-05 
     Eu-157   Pu-239   Fast      6.352970e-05   4.065900e-05 
     Eu-157   Pu-239   High      3.992190e-04   2.555000e-04 
     Eu-157   Pu-241   Thermal   4.230690e-06   2.707640e-06 
     Eu-157   Pu-241   Fast      1.413940e-05   9.049190e-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)
    -----------------------------------------------------------
     Eu-157    U-235   Thermal   6.141370e-05   4.920330e-06 
     Eu-157    U-235   Fast      1.056070e-04   3.386600e-05 
     Eu-157    U-235   High      3.754950e-04   8.623740e-05 
     Eu-157    U-238   Fast      4.139020e-04   1.324010e-04 
     Eu-157    U-238   High      8.043500e-04   1.285590e-04 
     Eu-157   Pu-239   Thermal   7.411060e-04   4.447350e-05 
     Eu-157   Pu-239   Fast      1.060510e-03   8.485300e-05 
     Eu-157   Pu-239   High      1.093530e-03   1.748520e-04 
     Eu-157   Pu-241   Thermal   1.353900e-03   5.414800e-05 
     Eu-157   Pu-241   Fast      1.627090e-03   5.210600e-04 
    -----------------------------------------------------------
    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