Level energy(keV)   Spin & Parity       
       ground state      1/2-                  
       3.97550E+01       7/2+                  
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)
     102.905497993 ± 0.000002610 (amu)  [mass excess = -88028.052 ± 2.431 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -543.020 ± 0.797 (keV) 
Strong Gamma-rays from Decay of Rh-103 (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 
         39.76            0.07         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 
       IT           56.114 M 20      
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Rh-103.
     Figures of cross sections, Rh-103:  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-103 (Z= 45, A=103), MT=  2 (Elastic scattering)
     Rh-103 (Z= 45, A=103), MT=  4 (Inelastic scattering)
     Rh-105 (Z= 45, A=105), MT= 17 (n,3n)
     Pd-104 (Z= 46, A=104), MT= 28 (n,np)
     Pd-104 (Z= 46, A=104), MT=104 (n,d)
     Pd-105 (Z= 46, A=105), MT= 32 (n,nd)
     Pd-105 (Z= 46, A=105), MT= 41 (n,2np)
     Pd-105 (Z= 46, A=105), MT=105 (n,t)
     Ag-107 (Z= 47, A=107), 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)
     Rh-103    U-235   Thermal   6.517260e-13   4.171050e-13 
     Rh-103    U-235   Fast      2.006580e-13   1.284210e-13 
     Rh-103    U-235   High      1.323900e-10   4.236500e-11 
     Rh-103    U-238   Fast      1.054130e-14   6.746430e-15 
     Rh-103    U-238   High      2.697930e-12   1.726680e-12 
     Rh-103   Pu-239   Thermal   3.408250e-10   2.181280e-10 
     Rh-103   Pu-239   Fast      3.002610e-10   1.921670e-10 
     Rh-103   Pu-239   High      5.677810e-08   3.633800e-08 
     Rh-103   Pu-241   Thermal   1.636170e-12   1.047150e-12 
     Rh-103   Pu-241   Fast      2.250930e-12   1.440590e-12 
     Rh-103m   U-235   Thermal   4.248470e-12   2.719020e-12 
     Rh-103m   U-235   Fast      1.499830e-12   9.598920e-13 
     Rh-103m   U-235   High      1.586960e-09   1.015660e-09 
     Rh-103m   U-238   Fast      7.879200e-14   5.042690e-14 
     Rh-103m   U-238   High      3.234020e-11   2.069770e-11 
     Rh-103m  Pu-239   Thermal   2.221770e-09   1.421930e-09 
     Rh-103m  Pu-239   Fast      2.244330e-09   1.436360e-09 
     Rh-103m  Pu-239   High      6.806000e-07   4.355840e-07 
     Rh-103m  Pu-241   Thermal   1.066580e-11   6.826120e-12 
     Rh-103m  Pu-241   Fast      1.682470e-11   1.076780e-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)
     Rh-103    U-235   Thermal   3.028690e-02   3.039190e-04 
     Rh-103    U-235   Fast      3.239800e-02   4.559920e-04 
     Rh-103    U-235   High      3.212970e-02   9.010780e-04 
     Rh-103    U-238   Fast      6.268170e-02   8.814480e-04 
     Rh-103    U-238   High      4.621080e-02   9.246570e-04 
     Rh-103   Pu-239   Thermal   6.999100e-02   1.399620e-03 
     Rh-103   Pu-239   Fast      6.833460e-02   9.571290e-04 
     Rh-103   Pu-239   High      5.214900e-02   2.084340e-03 
     Rh-103   Pu-241   Thermal   6.790690e-02   1.902540e-03 
     Rh-103   Pu-241   Fast      6.514150e-02   2.603930e-03 
     Rh-103m   U-235   Thermal   3.021120e-02   4.673890e-04 
     Rh-103m   U-235   Fast      3.231700e-02   4.930330e-04 
     Rh-103m   U-235   High      3.204940e-02   9.449530e-04 
     Rh-103m   U-238   Fast      6.252500e-02   9.570480e-04 
     Rh-103m   U-238   High      4.609530e-02   9.970620e-04 
     Rh-103m  Pu-239   Thermal   6.981600e-02   1.496700e-03 
     Rh-103m  Pu-239   Fast      6.816380e-02   1.098480e-03 
     Rh-103m  Pu-239   High      5.201860e-02   3.127580e-03 
     Rh-103m  Pu-241   Thermal   6.773710e-02   2.760320e-03 
     Rh-103m  Pu-241   Fast      6.497860e-02   3.904580e-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