44-Ru-105



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)
     104.907747645 ± 0.000002756 (amu)  [mass excess = -85932.515 ± 2.568 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     1918.035 ± 2.876 (keV) 
Strong Gamma-rays from Decay of Ru-105 (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 
  ----------------------------------------------------------
        469.37           17.55         B- 
        676.36           15.66         B- 
        724.30           47.3          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-           4.44 H 2         
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ru-105.
     Figures of cross sections, Ru-105:  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
     Ru-104 (Z= 44, A=104), MT=102 (n,γ)
     Ru-105 (Z= 44, A=105), MT=  2 (Elastic scattering)
     Ru-105 (Z= 44, A=105), MT=  4 (Inelastic scattering)
     Ru-106 (Z= 44, A=106), MT= 16 (n,2n)
     Rh-105 (Z= 45, A=105), MT=103 (n,p)
     Pd-107 (Z= 46, A=107), MT=106 (n,3He)
     Pd-108 (Z= 46, A=108), MT=107 (n,α)

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)
    -----------------------------------------------------------
     Ru-105    U-235   Thermal   1.108230e-09   7.092710e-10 
     Ru-105    U-235   Fast      1.007920e-09   6.450680e-10 
     Ru-105    U-235   High      9.924610e-05   6.351740e-05 
     Ru-105    U-238   Fast      3.601340e-06   2.304850e-06 
     Ru-105    U-238   High      2.822070e-05   1.806130e-05 
     Ru-105   Pu-239   Thermal   4.543880e-04   2.908090e-04 
     Ru-105   Pu-239   Fast      8.866460e-04   5.674540e-04 
     Ru-105   Pu-239   High      3.375140e-03   2.160090e-03 
     Ru-105   Pu-241   Thermal   8.909430e-05   5.702040e-05 
     Ru-105   Pu-241   Fast      1.399850e-04   8.959020e-05 
    -----------------------------------------------------------
    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)
    -----------------------------------------------------------
     Ru-105    U-235   Thermal   9.581860e-03   5.815720e-04 
     Ru-105    U-235   Fast      1.188340e-02   7.222030e-04 
     Ru-105    U-235   High      1.868220e-02   2.995530e-03 
     Ru-105    U-238   Fast      4.019430e-02   1.178250e-03 
     Ru-105    U-238   High      3.200240e-02   9.139610e-04 
     Ru-105   Pu-239   Thermal   5.632090e-02   1.584380e-03 
     Ru-105   Pu-239   Fast      5.352310e-02   2.146020e-03 
     Ru-105   Pu-239   High      4.265400e-02   6.827220e-03 
     Ru-105   Pu-241   Thermal   6.053230e-02   3.650710e-03 
     Ru-105   Pu-241   Fast      6.555150e-02   1.053730e-02 
    -----------------------------------------------------------
    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