37-Rb-85



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)
     84.91178973790 ± 0.00000000535 (amu)  [mass excess = -82167.33008 ± 0.00498 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1064.054 ± 2.813 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Rb-85.
     Figures of cross sections, Rb-85:  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- 85 (Z= 37, A= 85), MT=  2 (Elastic scattering)
     Rb- 85 (Z= 37, A= 85), MT=  4 (Inelastic scattering)
     Rb- 86 (Z= 37, A= 86), MT= 16 (n,2n)
     Rb- 87 (Z= 37, A= 87), MT= 17 (n,3n)
     Sr- 86 (Z= 38, A= 86), MT= 28 (n,np)
     Sr- 86 (Z= 38, A= 86), MT=104 (n,d)
     Sr- 87 (Z= 38, A= 87), MT= 32 (n,nd)
     Sr- 87 (Z= 38, A= 87), MT=105 (n,t)
     Y - 89 (Z= 39, A= 89), 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- 85    U-235   Thermal   2.371220e-05   1.517580e-05 
     Rb- 85    U-235   Fast      1.447020e-08   9.260880e-09 
     Rb- 85    U-235   High      2.002740e-06   1.281750e-06 
     Rb- 85    U-238   Fast      1.100410e-09   3.521310e-10 
     Rb- 85    U-238   High      6.657250e-08   4.260640e-08 
     Rb- 85   Pu-239   Thermal   4.239330e-07   2.713180e-07 
     Rb- 85   Pu-239   Fast      1.139820e-06   3.647410e-07 
     Rb- 85   Pu-239   High      4.002600e-06   2.561660e-06 
     Rb- 85   Pu-241   Thermal   2.700440e-08   1.728280e-08 
     Rb- 85   Pu-241   Fast      7.044700e-09   4.508610e-09 
    -----------------------------------------------------------
    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- 85    U-235   Thermal   1.330740e-02   1.297140e-04 
     Rb- 85    U-235   Fast      1.363160e-02   9.566490e-05 
     Rb- 85    U-235   High      1.671530e-02   4.696380e-04 
     Rb- 85    U-238   Fast      7.520400e-03   1.165840e-04 
     Rb- 85    U-238   High      1.013220e-02   1.584150e-04 
     Rb- 85   Pu-239   Thermal   5.741900e-03   2.013360e-05 
     Rb- 85   Pu-239   Fast      6.044730e-03   3.035140e-05 
     Rb- 85   Pu-239   High      9.676330e-03   3.867820e-04 
     Rb- 85   Pu-241   Thermal   4.070850e-03   5.722180e-05 
     Rb- 85   Pu-241   Fast      4.472490e-03   8.958120e-05 
    -----------------------------------------------------------
    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