64-Gd-158



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      0+                    
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)
     157.924112348 ± 0.000001742 (amu)  [mass excess = -70688.892 ± 1.623 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1218.952 ± 0.993 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Gd-158.
     Figures of cross sections, Gd-158:  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-157 (Z= 64, A=157), MT=102 (n,γ)
     Gd-158 (Z= 64, A=158), MT=  2 (Elastic scattering)
     Gd-158 (Z= 64, A=158), MT=  4 (Inelastic scattering)
     Gd-160 (Z= 64, A=160), MT= 17 (n,3n)
     Tb-159 (Z= 65, A=159), MT= 28 (n,np)
     Tb-159 (Z= 65, A=159), MT=104 (n,d)
     Tb-160 (Z= 65, A=160), MT= 32 (n,nd)
     Tb-160 (Z= 65, A=160), MT= 41 (n,2np)
     Tb-160 (Z= 65, A=160), MT=105 (n,t)
     Dy-160 (Z= 66, A=160), MT=106 (n,3He)
     Dy-161 (Z= 66, A=161), MT=107 (n,α)
     Dy-162 (Z= 66, A=162), MT= 22 (n,nα)
     Dy-163 (Z= 66, A=163), 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-158    U-235   Thermal   1.477650e-08   9.456940e-09 
     Gd-158    U-235   Fast      8.761910e-09   5.607620e-09 
     Gd-158    U-235   High      6.098360e-06   3.902950e-06 
     Gd-158    U-238   Fast      1.110420e-09   7.106650e-10 
     Gd-158    U-238   High      1.011100e-07   6.471050e-08 
     Gd-158   Pu-239   Thermal   1.519760e-06   9.726470e-07 
     Gd-158   Pu-239   Fast      3.739390e-06   2.393210e-06 
     Gd-158   Pu-239   High      8.338410e-05   5.336580e-05 
     Gd-158   Pu-241   Thermal   5.620910e-08   3.597380e-08 
     Gd-158   Pu-241   Fast      3.267540e-07   2.091230e-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)
    -----------------------------------------------------------
     Gd-158    U-235   Thermal   3.280190e-05   3.614770e-06 
     Gd-158    U-235   Fast      6.481890e-05   1.039100e-05 
     Gd-158    U-235   High      2.350180e-04   2.581640e-05 
     Gd-158    U-238   Fast      1.849430e-04   2.957950e-05 
     Gd-158    U-238   High      4.263930e-04   6.814910e-05 
     Gd-158   Pu-239   Thermal   4.143170e-04   6.630160e-05 
     Gd-158   Pu-239   Fast      6.564680e-04   1.050490e-04 
     Gd-158   Pu-239   High      7.309060e-04   1.168730e-04 
     Gd-158   Pu-241   Thermal   9.226000e-04   2.121610e-04 
     Gd-158   Pu-241   Fast      1.118650e-03   1.791190e-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