37-Rb-87



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      3/2-                  
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)
     86.909180531 ± 0.000000006 (amu)  [mass excess = -84597.790 ± 0.006 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     282.243 ± 1.075 (keV) 
Decay data(Chart of the Nuclides 2014)
     Decay mode     Half-life 
       B-           4.81E10 Y 9      
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Rb-87.
     Figures of cross sections, Rb-87:  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
     Rb- 86 (Z= 37, A= 86), MT=102 (n,γ)
     Rb- 87 (Z= 37, A= 87), MT=  2 (Elastic scattering)
     Rb- 87 (Z= 37, A= 87), MT=  4 (Inelastic scattering)
     Sr- 87 (Z= 38, A= 87), MT=103 (n,p)
     Sr- 88 (Z= 38, A= 88), MT= 28 (n,np)
     Sr- 88 (Z= 38, A= 88), MT=104 (n,d)
     Sr- 89 (Z= 38, A= 89), MT= 32 (n,nd)
     Sr- 89 (Z= 38, A= 89), MT=105 (n,t)
     Y - 89 (Z= 39, A= 89), MT=106 (n,3He)
     Y - 90 (Z= 39, A= 90), MT=107 (n,α)
     Y - 91 (Z= 39, A= 91), 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)
    -----------------------------------------------------------
     Rb- 87    U-235   Thermal   2.498020e-05   1.598740e-05 
     Rb- 87    U-235   Fast      1.328260e-05   8.500850e-06 
     Rb- 87    U-235   High      2.043100e-04   1.307580e-04 
     Rb- 87    U-238   Fast      1.440540e-06   4.609720e-07 
     Rb- 87    U-238   High      1.897070e-05   1.214130e-05 
     Rb- 87   Pu-239   Thermal   1.465970e-04   9.382200e-05 
     Rb- 87   Pu-239   Fast      6.538940e-05   4.184930e-05 
     Rb- 87   Pu-239   High      2.739880e-04   1.753520e-04 
     Rb- 87   Pu-241   Thermal   1.468240e-05   9.396710e-06 
     Rb- 87   Pu-241   Fast      5.925540e-06   3.792350e-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)
    -----------------------------------------------------------
     Rb- 87    U-235   Thermal   2.591430e-02   3.382120e-04 
     Rb- 87    U-235   Fast      2.540520e-02   2.565100e-04 
     Rb- 87    U-235   High      2.456610e-02   9.821420e-04 
     Rb- 87    U-238   Fast      1.632320e-02   1.762000e-04 
     Rb- 87    U-238   High      1.693350e-02   3.443350e-04 
     Rb- 87   Pu-239   Thermal   1.003970e-02   5.020220e-05 
     Rb- 87   Pu-239   Fast      1.043460e-02   1.043410e-04 
     Rb- 87   Pu-239   High      1.313190e-02   5.248630e-04 
     Rb- 87   Pu-241   Thermal   7.533590e-03   1.506590e-04 
     Rb- 87   Pu-241   Fast      8.021290e-03   3.208000e-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