40-Zr-93



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)
     92.906469947 ± 0.000001952 (amu)  [mass excess = -87122.683 ± 1.819 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     90.301 ± 1.549 (keV) 
Strong Gamma-rays from Decay of Zr- 93 (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 
  ----------------------------------------------------------
         30.77            --           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-           1.61E+6 Y 10     
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Zr-93.
     Figures of cross sections, Zr-93:  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
     Zr- 92 (Z= 40, A= 92), MT=102 (n,γ)
     Zr- 93 (Z= 40, A= 93), MT=  2 (Elastic scattering)
     Zr- 93 (Z= 40, A= 93), MT=  4 (Inelastic scattering)
     Zr- 94 (Z= 40, A= 94), MT= 16 (n,2n)
     Zr- 95 (Z= 40, A= 95), MT= 17 (n,3n)
     Nb- 93 (Z= 41, A= 93), MT=103 (n,p)
     Nb- 94 (Z= 41, A= 94), MT= 28 (n,np)
     Nb- 94 (Z= 41, A= 94), MT=104 (n,d)
     Nb- 95 (Z= 41, A= 95), MT= 32 (n,nd)
     Nb- 95 (Z= 41, A= 95), MT=105 (n,t)
     Mo- 95 (Z= 42, A= 95), MT=106 (n,3He)
     Mo- 96 (Z= 42, A= 96), MT=107 (n,α)
     Mo- 97 (Z= 42, A= 97), MT= 22 (n,nα)

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)
    -----------------------------------------------------------
     Zr- 93    U-235   Thermal   1.367820e-06   8.754060e-07 
     Zr- 93    U-235   Fast      4.919850e-07   3.148700e-07 
     Zr- 93    U-235   High      3.848270e-05   2.462890e-05 
     Zr- 93    U-238   Fast      2.170810e-08   1.389320e-08 
     Zr- 93    U-238   High      8.799580e-07   5.631730e-07 
     Zr- 93   Pu-239   Thermal   1.685740e-05   1.078870e-05 
     Zr- 93   Pu-239   Fast      1.146810e-05   7.339610e-06 
     Zr- 93   Pu-239   High      1.030070e-04   6.592440e-05 
     Zr- 93   Pu-241   Thermal   6.981120e-07   4.467920e-07 
     Zr- 93   Pu-241   Fast      4.256800e-07   2.724350e-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)
    -----------------------------------------------------------
     Zr- 93    U-235   Thermal   6.339730e-02   4.490650e-04 
     Zr- 93    U-235   Fast      6.239500e-02   4.611580e-04 
     Zr- 93    U-235   High      5.203510e-02   3.117620e-03 
     Zr- 93    U-238   Fast      4.918390e-02   9.839790e-04 
     Zr- 93    U-238   High      4.538910e-02   1.271920e-03 
     Zr- 93   Pu-239   Thermal   3.797780e-02   2.658390e-04 
     Zr- 93   Pu-239   Fast      3.826360e-02   2.678870e-04 
     Zr- 93   Pu-239   High      3.232100e-02   3.551900e-03 
     Zr- 93   Pu-241   Thermal   2.980460e-02   4.176260e-04 
     Zr- 93   Pu-241   Fast      2.981070e-02   3.279100e-03 
    -----------------------------------------------------------
    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