Level energy(keV)   Spin & Parity       
       ground state      7/2+                  
       1.29570E+02       1/2-                  
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)
     104.905688549 ± 0.000002694 (amu)  [mass excess = -87850.550 ± 2.510 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     567.208 ± 2.352 (keV) 
Strong Gamma-rays from Decay of Rh-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 
        280.1             0.17         B- 
        306.1             5.1          B- 
        318.9            19.1          B- 
        129.57            --           IT 
     *: 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-           35.36 H 6        
       IT           40 S AP          
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Rh-105.
     Figures of cross sections, Rh-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
     Rh-105 (Z= 45, A=105), MT=  2 (Elastic scattering)
     Rh-105 (Z= 45, A=105), MT=  4 (Inelastic scattering)
     Pd-105 (Z= 46, A=105), MT=103 (n,p)
     Pd-106 (Z= 46, A=106), MT= 28 (n,np)
     Pd-106 (Z= 46, A=106), MT=104 (n,d)
     Pd-107 (Z= 46, A=107), MT= 32 (n,nd)
     Pd-107 (Z= 46, A=107), MT= 41 (n,2np)
     Pd-107 (Z= 46, A=107), MT=105 (n,t)
     Ag-107 (Z= 47, A=107), MT=106 (n,3He)
     Ag-109 (Z= 47, A=109), MT= 22 (n,nα)
     Ag-110 (Z= 47, A=110), MT= 24 (n,2nα)

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)
     Rh-105    U-235   Fast      6.161280e-10   1.971610e-10 
     Rh-105    U-235   High      4.099130e-08   1.311720e-08 
     Rh-105    U-238   Fast      4.471640e-10   2.861850e-10 
     Rh-105    U-238   High      7.872530e-09   2.519210e-09 
     Rh-105   Pu-239   Thermal   1.375710e-06   8.804560e-07 
     Rh-105   Pu-239   Fast      1.633200e-06   1.045250e-06 
     Rh-105   Pu-239   High      7.251170e-05   4.640750e-05 
     Rh-105   Pu-241   Thermal   3.080080e-08   1.971250e-08 
     Rh-105   Pu-241   Fast      6.430240e-08   4.115350e-08 
     Rh-105m   U-235   Fast      8.242990e-11   5.275510e-11 
     Rh-105m   U-235   High      3.419640e-09   2.188570e-09 
     Rh-105m   U-238   Fast      5.982470e-11   3.828780e-11 
     Rh-105m   U-238   High      6.567550e-10   4.203250e-10 
     Rh-105m  Pu-239   Thermal   2.110370e-07   1.350640e-07 
     Rh-105m  Pu-239   Fast      2.185000e-07   1.398410e-07 
     Rh-105m  Pu-239   High      6.049190e-06   3.871480e-06 
     Rh-105m  Pu-241   Thermal   4.724930e-09   3.023950e-09 
     Rh-105m  Pu-241   Fast      8.602810e-09   5.505800e-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)
     Rh-105    U-235   Thermal   9.581860e-03   5.973970e-05 
     Rh-105    U-235   Fast      1.188340e-02   3.443290e-04 
     Rh-105    U-235   High      1.868220e-02   1.123890e-03 
     Rh-105    U-238   Fast      4.019430e-02   8.706410e-04 
     Rh-105    U-238   High      3.200240e-02   6.619590e-04 
     Rh-105   Pu-239   Thermal   5.632240e-02   1.134600e-03 
     Rh-105   Pu-239   Fast      5.352490e-02   1.503490e-03 
     Rh-105   Pu-239   High      4.273260e-02   2.564920e-03 
     Rh-105   Pu-241   Thermal   6.053230e-02   1.713870e-03 
     Rh-105   Pu-241   Fast      6.555150e-02   7.247270e-03 
     Rh-105m   U-235   Thermal   2.730830e-03   1.275900e-04 
     Rh-105m   U-235   Fast      3.386760e-03   2.492370e-04 
     Rh-105m   U-235   High      5.324430e-03   1.193460e-03 
     Rh-105m   U-238   Fast      1.145540e-02   6.008070e-04 
     Rh-105m   U-238   High      9.120690e-03   5.007540e-04 
     Rh-105m  Pu-239   Thermal   1.605170e-02   1.016710e-03 
     Rh-105m  Pu-239   Fast      1.525430e-02   9.713100e-04 
     Rh-105m  Pu-239   High      1.216250e-02   1.950730e-03 
     Rh-105m  Pu-241   Thermal   1.725170e-02   1.300980e-03 
     Rh-105m  Pu-241   Fast      1.868220e-02   2.985160e-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