63-Eu-153



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)
     152.921238003 ± 0.000001846 (amu)  [mass excess = -73366.327 ± 1.720 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -484.399 ± 0.702 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Eu-153.
     Figures of cross sections, Eu-153:  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-152 (Z= 63, A=152), MT=102 (n,γ)
     Eu-153 (Z= 63, A=153), MT=  2 (Elastic scattering)
     Eu-153 (Z= 63, A=153), MT=  4 (Inelastic scattering)
     Eu-154 (Z= 63, A=154), MT= 16 (n,2n)
     Eu-155 (Z= 63, A=155), MT= 17 (n,3n)
     Gd-153 (Z= 64, A=153), MT=103 (n,p)
     Gd-154 (Z= 64, A=154), MT= 28 (n,np)
     Gd-154 (Z= 64, A=154), MT=104 (n,d)
     Gd-155 (Z= 64, A=155), MT= 32 (n,nd)
     Gd-155 (Z= 64, A=155), MT= 41 (n,2np)
     Gd-155 (Z= 64, A=155), MT=105 (n,t)

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-153    U-235   Thermal   2.326300e-09   7.444140e-10 
     Eu-153    U-235   Fast      4.590520e-11   2.937930e-11 
     Eu-153    U-235   High      5.036900e-07   3.223620e-07 
     Eu-153    U-238   Fast      3.031130e-12   1.939920e-12 
     Eu-153    U-238   High      1.391520e-09   8.905700e-10 
     Eu-153   Pu-239   Thermal   2.509610e-08   1.606150e-08 
     Eu-153   Pu-239   Fast      4.489270e-08   2.873140e-08 
     Eu-153   Pu-239   High      1.388900e-05   8.888960e-06 
     Eu-153   Pu-241   Thermal   1.110180e-10   7.105140e-11 
     Eu-153   Pu-241   Fast      6.055450e-10   3.875490e-10 
    -----------------------------------------------------------
    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-153    U-235   Thermal   1.580380e-03   4.438360e-05 
     Eu-153    U-235   Fast      1.667130e-03   4.690050e-05 
     Eu-153    U-235   High      2.038900e-03   2.239670e-04 
     Eu-153    U-238   Fast      4.149420e-03   8.297190e-05 
     Eu-153    U-238   High      3.923480e-03   2.351920e-04 
     Eu-153   Pu-239   Thermal   3.612010e-03   2.167540e-04 
     Eu-153   Pu-239   Fast      4.257780e-03   1.703370e-04 
     Eu-153   Pu-239   High      4.580150e-03   5.034980e-04 
     Eu-153   Pu-241   Thermal   5.406710e-03   2.162350e-04 
     Eu-153   Pu-241   Fast      5.501840e-03   2.202780e-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