38-Sr-86



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)
     85.909260608 ± 0.000001154 (amu)  [mass excess = -84523.199 ± 1.076 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -5240.000 ± 14.142 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Sr-86.
     Figures of cross sections, Sr-86:  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- 86 (Z= 38, A= 86), MT=  2 (Elastic scattering)
     Sr- 86 (Z= 38, A= 86), MT=  4 (Inelastic scattering)
     Sr- 87 (Z= 38, A= 87), MT= 16 (n,2n)
     Zr- 90 (Z= 40, A= 90), 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- 86    U-235   Thermal   1.188110e-10   7.603890e-11 
     Sr- 86    U-235   Fast      6.726110e-11   4.304710e-11 
     Sr- 86    U-235   High      3.665030e-08   2.345610e-08 
     Sr- 86    U-238   Fast      1.370510e-12   8.771270e-13 
     Sr- 86    U-238   High      5.746250e-10   3.677610e-10 
     Sr- 86   Pu-239   Thermal   1.009840e-08   6.462980e-09 
     Sr- 86   Pu-239   Fast      3.579420e-09   2.290830e-09 
     Sr- 86   Pu-239   High      1.390900e-07   8.901770e-08 
     Sr- 86   Pu-241   Thermal   1.620260e-10   1.036970e-10 
     Sr- 86   Pu-241   Fast      3.707210e-11   2.372620e-11 
    -----------------------------------------------------------
    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- 86    U-235   Thermal   6.451300e-08   4.128840e-08 
     Sr- 86    U-235   Fast      4.371430e-07   2.797720e-07 
     Sr- 86    U-235   High      1.618740e-06   1.035990e-06 
     Sr- 86    U-238   Fast      2.801040e-08   1.792010e-08 
     Sr- 86    U-238   High      1.297090e-07   8.301340e-08 
     Sr- 86   Pu-239   Thermal   1.839720e-06   1.177420e-06 
     Sr- 86   Pu-239   Fast      4.732580e-06   3.028850e-06 
     Sr- 86   Pu-239   High      3.768160e-05   2.410240e-05 
     Sr- 86   Pu-241   Thermal   8.032520e-07   5.139200e-07 
     Sr- 86   Pu-241   Fast      2.178620e-07   1.394320e-07 
    -----------------------------------------------------------
    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