64-Gd-155



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      3/2-                  
       1.21050E+02       11/2-                 
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)
     154.922630473 ± 0.000001742 (amu)  [mass excess = -72069.250 ± 1.624 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -819.784 ± 9.789 (keV) 
Strong Gamma-rays from Decay of Gd-155 (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 
  ----------------------------------------------------------
         13.47            7.1          IT 
         21.04            0.04         IT 
         86.55           70.           IT 
  ----------------------------------------------------------
     *: 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 
       IT           31.97 MS 27      
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Gd-155.
     Figures of cross sections, Gd-155:  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
     Gd-154 (Z= 64, A=154), MT=102 (n,γ)
     Gd-155 (Z= 64, A=155), MT=  2 (Elastic scattering)
     Gd-155 (Z= 64, A=155), MT=  4 (Inelastic scattering)
     Gd-156 (Z= 64, A=156), MT= 16 (n,2n)
     Gd-157 (Z= 64, A=157), MT= 17 (n,3n)
     Dy-158 (Z= 66, A=158), MT=107 (n,α)
     Dy-159 (Z= 66, A=159), MT= 22 (n,nα)
     Dy-160 (Z= 66, A=160), MT= 24 (n,2nα)

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)
    -----------------------------------------------------------
     Gd-155    U-235   Thermal   4.073510e-12   2.607050e-12 
     Gd-155    U-235   Fast      1.327260e-12   8.494470e-13 
     Gd-155    U-235   High      5.848020e-08   3.742730e-08 
     Gd-155    U-238   Fast      8.043000e-14   5.147520e-14 
     Gd-155    U-238   High      6.356930e-11   4.068430e-11 
     Gd-155   Pu-239   Thermal   1.659740e-09   1.062240e-09 
     Gd-155   Pu-239   Fast      5.239150e-09   3.353060e-09 
     Gd-155   Pu-239   High      2.961920e-06   1.895630e-06 
     Gd-155   Pu-241   Thermal   4.010650e-12   2.566820e-12 
     Gd-155   Pu-241   Fast      5.216080e-11   3.338290e-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)
    -----------------------------------------------------------
     Gd-155    U-235   Thermal   3.207940e-04   1.286660e-05 
     Gd-155    U-235   Fast      3.937380e-04   4.342980e-05 
     Gd-155    U-235   High      7.883100e-04   8.659920e-05 
     Gd-155    U-238   Fast      1.412620e-03   1.556880e-04 
     Gd-155    U-238   High      1.552620e-03   2.484120e-04 
     Gd-155   Pu-239   Thermal   1.656840e-03   1.822940e-04 
     Gd-155   Pu-239   Fast      2.087750e-03   2.296990e-04 
     Gd-155   Pu-239   High      2.332980e-03   2.564690e-04 
     Gd-155   Pu-241   Thermal   2.412900e-03   1.931350e-04 
     Gd-155   Pu-241   Fast      3.354650e-03   5.373650e-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