38-Sr-89



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)
     88.907451095 ± 0.000001168 (amu)  [mass excess = -86208.750 ± 1.089 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     1500.401 ± 2.335 (keV) 
Strong Gamma-rays from Decay of Sr- 89 (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 
  ----------------------------------------------------------
        908.96          1.E-02         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-           50.53 D 7        
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Sr-89.
     Figures of cross sections, Sr-89:  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
     Sr- 88 (Z= 38, A= 88), MT=102 (n,γ)
     Sr- 89 (Z= 38, A= 89), MT=  2 (Elastic scattering)
     Sr- 89 (Z= 38, A= 89), MT=  4 (Inelastic scattering)
     Sr- 90 (Z= 38, A= 90), MT= 16 (n,2n)
     Y - 89 (Z= 39, A= 89), MT=103 (n,p)
     Y - 90 (Z= 39, A= 90), MT= 28 (n,np)
     Y - 90 (Z= 39, A= 90), MT=104 (n,d)
     Y - 91 (Z= 39, A= 91), MT= 32 (n,nd)
     Y - 91 (Z= 39, A= 91), MT=105 (n,t)
     Zr- 90 (Z= 40, A= 90), MT=111 (n,2p)
     Zr- 91 (Z= 40, A= 91), MT=106 (n,3He)
     Zr- 92 (Z= 40, A= 92), MT=107 (n,α)
     Zr- 93 (Z= 40, A= 93), 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)
    -----------------------------------------------------------
     Sr- 89    U-235   Thermal   1.749320e-04   1.119560e-04 
     Sr- 89    U-235   Fast      8.302860e-06   5.313830e-06 
     Sr- 89    U-235   High      1.766720e-04   1.130700e-04 
     Sr- 89    U-238   Fast      4.631730e-07   2.964310e-07 
     Sr- 89    U-238   High      9.210030e-06   5.894420e-06 
     Sr- 89   Pu-239   Thermal   1.510160e-04   9.665040e-05 
     Sr- 89   Pu-239   Fast      5.052180e-05   3.233390e-05 
     Sr- 89   Pu-239   High      2.671930e-04   1.710040e-04 
     Sr- 89   Pu-241   Thermal   6.991120e-06   4.474330e-06 
     Sr- 89   Pu-241   Fast      3.597290e-06   2.302270e-06 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Sr- 89    U-235   Thermal   4.725010e-02   4.795440e-04 
     Sr- 89    U-235   Fast      4.363980e-02   6.199340e-04 
     Sr- 89    U-235   High      4.127840e-02   1.155520e-03 
     Sr- 89    U-238   Fast      2.761730e-02   3.866050e-04 
     Sr- 89    U-238   High      2.924200e-02   8.184800e-04 
     Sr- 89   Pu-239   Thermal   1.722480e-02   4.823910e-04 
     Sr- 89   Pu-239   Fast      1.724750e-02   3.451100e-04 
     Sr- 89   Pu-239   High      2.069260e-02   1.241030e-03 
     Sr- 89   Pu-241   Thermal   1.233130e-02   4.932280e-04 
     Sr- 89   Pu-241   Fast      1.280860e-02   1.410450e-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