Level energy(keV)   Spin & Parity       
       ground state      0+                    
       2.31899E+03       5-                    
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)
     89.904697659 ± 0.000001984 (amu)  [mass excess = -88773.558 ± 1.849 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -6111.336 ± 3.366 (keV) 
Strong Gamma-rays from Decay of Zr- 90 (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 
        132.72            4.18         IT 
       2186.24           18.18         IT 
       2318.96           83.           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           809.2 MS 20      
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Zr-90.
     Figures of cross sections, Zr-90:  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- 90 (Z= 40, A= 90), MT=  2 (Elastic scattering)
     Zr- 90 (Z= 40, A= 90), MT=  4 (Inelastic scattering)
     Zr- 91 (Z= 40, A= 91), MT= 16 (n,2n)
     Zr- 92 (Z= 40, A= 92), MT= 17 (n,3n)
     Mo- 92 (Z= 42, A= 92), MT=106 (n,3He)
     Mo- 94 (Z= 42, A= 94), 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- 90    U-235   Thermal   8.032000e-13   5.140500e-13 
     Zr- 90    U-235   Fast      3.037530e-13   1.944020e-13 
     Zr- 90    U-235   High      7.309810e-10   4.678290e-10 
     Zr- 90    U-238   Fast      5.987230e-15   3.831840e-15 
     Zr- 90    U-238   High      2.092780e-12   1.339380e-12 
     Zr- 90   Pu-239   Thermal   1.153740e-10   7.383940e-11 
     Zr- 90   Pu-239   Fast      4.017850e-11   2.571420e-11 
     Zr- 90   Pu-239   High      4.941300e-09   3.162430e-09 
     Zr- 90   Pu-241   Thermal   6.433040e-13   4.117150e-13 
     Zr- 90   Pu-241   Fast      2.580160e-13   1.651300e-13 
     Zr- 90m   U-235   Thermal   3.380130e-12   2.163300e-12 
     Zr- 90m   U-235   Fast      1.472580e-12   9.424510e-13 
     Zr- 90m   U-235   High      5.737880e-09   3.672250e-09 
     Zr- 90m   U-238   Fast      2.902580e-14   1.857660e-14 
     Zr- 90m   U-238   High      1.642740e-11   1.051350e-11 
     Zr- 90m  Pu-239   Thermal   4.855310e-10   3.107410e-10 
     Zr- 90m  Pu-239   Fast      1.947840e-10   1.246610e-10 
     Zr- 90m  Pu-239   High      3.878710e-08   2.482370e-08 
     Zr- 90m  Pu-241   Thermal   2.707240e-12   1.732630e-12 
     Zr- 90m  Pu-241   Fast      1.250850e-12   8.005440e-13 
    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- 90    U-235   Thermal   5.772090e-02   5.865160e-04 
     Zr- 90    U-235   Fast      5.452160e-02   4.035290e-04 
     Zr- 90    U-235   High      4.599230e-02   1.287430e-03 
     Zr- 90    U-238   Fast      3.246620e-02   4.545850e-04 
     Zr- 90    U-238   High      3.191430e-02   8.932740e-04 
     Zr- 90   Pu-239   Thermal   2.103390e-02   4.209450e-04 
     Zr- 90   Pu-239   Fast      2.047910e-02   1.434990e-04 
     Zr- 90   Pu-239   High      2.103750e-02   2.313040e-03 
     Zr- 90   Pu-241   Thermal   1.535540e-02   2.150330e-04 
     Zr- 90   Pu-241   Fast      1.549330e-02   3.105910e-04 
     Zr- 90m   U-235   Thermal   1.022120e-10   6.541600e-11 
     Zr- 90m   U-235   Fast      5.538010e-11   3.544330e-11 
     Zr- 90m   U-235   High      1.988330e-08   1.272530e-08 
     Zr- 90m   U-238   Fast      2.889920e-12   1.849550e-12 
     Zr- 90m   U-238   High      2.256170e-10   1.443950e-10 
     Zr- 90m  Pu-239   Thermal   2.615070e-09   1.673650e-09 
     Zr- 90m  Pu-239   Fast      1.340880e-09   8.581620e-10 
     Zr- 90m  Pu-239   High      6.753480e-08   3.799080e-08 
     Zr- 90m  Pu-241   Thermal   7.963780e-11   5.096820e-11 
     Zr- 90m  Pu-241   Fast      3.535470e-11   2.262700e-11 
    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