64-Gd-156



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)
     155.922131241 ± 0.000001742 (amu)  [mass excess = -72534.282 ± 1.624 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -2444.184 ± 3.681 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Gd-156.
     Figures of cross sections, Gd-156:  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-155 (Z= 64, A=155), MT=102 (n,γ)
     Gd-156 (Z= 64, A=156), MT=  2 (Elastic scattering)
     Gd-156 (Z= 64, A=156), MT=  4 (Inelastic scattering)
     Gd-157 (Z= 64, A=157), MT= 16 (n,2n)
     Gd-158 (Z= 64, A=158), MT= 17 (n,3n)
     Tb-159 (Z= 65, A=159), MT= 33 (n,nt)
     Dy-158 (Z= 66, A=158), MT=106 (n,3He)
     Dy-159 (Z= 66, A=159), MT=107 (n,α)
     Dy-160 (Z= 66, A=160), MT= 22 (n,nα)
     Dy-161 (Z= 66, A=161), 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-156    U-235   Thermal   1.427730e-10   9.137450e-11 
     Gd-156    U-235   Fast      3.911930e-11   2.503630e-11 
     Gd-156    U-235   High      4.416050e-07   2.826270e-07 
     Gd-156    U-238   Fast      3.571330e-12   2.285650e-12 
     Gd-156    U-238   High      1.011100e-09   6.471050e-10 
     Gd-156   Pu-239   Thermal   3.939380e-08   2.521200e-08 
     Gd-156   Pu-239   Fast      1.319790e-08   4.223320e-09 
     Gd-156   Pu-239   High      1.743130e-05   1.115600e-05 
     Gd-156   Pu-241   Thermal   1.530250e-10   9.793580e-11 
     Gd-156   Pu-241   Fast      1.938540e-09   1.240670e-09 
    -----------------------------------------------------------
    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-156    U-235   Thermal   1.483040e-04   4.164990e-06 
     Gd-156    U-235   Fast      2.021700e-04   4.073310e-06 
     Gd-156    U-235   High      5.797700e-04   1.623220e-05 
     Gd-156    U-238   Fast      7.606120e-04   1.520920e-05 
     Gd-156    U-238   High      1.144930e-03   3.204770e-05 
     Gd-156   Pu-239   Thermal   1.239990e-03   4.960690e-05 
     Gd-156   Pu-239   Fast      1.547290e-03   6.190090e-05 
     Gd-156   Pu-239   High      2.141110e-03   1.283910e-04 
     Gd-156   Pu-241   Thermal   1.721520e-03   4.819580e-05 
     Gd-156   Pu-241   Fast      2.440680e-03   3.908060e-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