Level energy(keV)   Spin & Parity       
       ground state      0-                    
       5.90300E+01       3-                    
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)
     143.913310859 ± 0.000003233 (amu)  [mass excess = -80750.415 ± 3.012 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     2997.440 ± 2.400 (keV) 
Strong Gamma-rays from Decay of Pr-144 (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 
         59.03            --           IT 
        617.8             0.02         B- 
       1631.36            0.03         B- 
       1885.3             0.01         B- 
        696.51            1.34         B- 
       1489.16            0.28         B- 
       2185.66            0.69         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-           17.28 M 5        
       B-           7.2 M 3          
       IT           7.2 M 3          
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Pr-143 (Z= 59, A=143), MT=102 (n,γ)
     Nd-144 (Z= 60, A=144), MT=103 (n,p)
     Nd-145 (Z= 60, A=145), MT= 28 (n,np)
     Nd-145 (Z= 60, A=145), MT=104 (n,d)
     Nd-146 (Z= 60, A=146), MT= 32 (n,nd)
     Nd-146 (Z= 60, A=146), MT=105 (n,t)
     Nd-147 (Z= 60, A=147), MT= 33 (n,nt)
     Pm-147 (Z= 61, A=147), MT=107 (n,α)
     Pm-148 (Z= 61, A=148), MT= 22 (n,nα)
     Pm-148 (Z= 61, A=148), MT= 22 (n,nα)
     Pm-149 (Z= 61, A=149), 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)
     Pr-144    U-235   Thermal   1.434950e-08   9.183640e-09 
     Pr-144    U-235   Fast      4.743700e-09   3.035960e-09 
     Pr-144    U-235   High      2.013620e-06   1.288720e-06 
     Pr-144    U-238   Fast      2.964810e-10   1.897470e-10 
     Pr-144    U-238   High      1.920730e-08   1.229270e-08 
     Pr-144   Pu-239   Thermal   3.691980e-07   2.362870e-07 
     Pr-144   Pu-239   Fast      5.045480e-07   3.229110e-07 
     Pr-144   Pu-239   High      1.396100e-05   8.935010e-06 
     Pr-144   Pu-241   Thermal   7.834820e-09   5.014290e-09 
     Pr-144   Pu-241   Fast      1.349120e-08   8.634340e-09 
     Pr-144m   U-235   Thermal   1.277240e-07   8.174360e-08 
     Pr-144m   U-235   Fast      4.855630e-08   3.107600e-08 
     Pr-144m   U-235   High      3.270400e-05   2.093050e-05 
     Pr-144m   U-238   Fast      3.034760e-09   1.942240e-09 
     Pr-144m   U-238   High      3.119530e-07   1.996500e-07 
     Pr-144m  Pu-239   Thermal   3.286230e-06   2.103180e-06 
     Pr-144m  Pu-239   Fast      5.164530e-06   3.305300e-06 
     Pr-144m  Pu-239   High      2.267450e-04   1.451170e-04 
     Pr-144m  Pu-241   Thermal   6.973760e-08   4.463220e-08 
     Pr-144m  Pu-241   Fast      1.380950e-07   8.838070e-08 
    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)
     Pr-144    U-235   Thermal   5.491350e-02   2.869830e-04 
     Pr-144    U-235   Fast      5.278490e-02   5.359990e-04 
     Pr-144    U-235   High      3.176830e-02   8.894500e-04 
     Pr-144    U-238   Fast      4.554210e-02   4.590730e-04 
     Pr-144    U-238   High      3.728310e-02   1.043830e-03 
     Pr-144   Pu-239   Thermal   3.739180e-02   1.870680e-04 
     Pr-144   Pu-239   Fast      3.672330e-02   2.571580e-04 
     Pr-144   Pu-239   High      2.706040e-02   1.081850e-03 
     Pr-144   Pu-241   Thermal   4.228500e-02   4.228890e-04 
     Pr-144   Pu-241   Fast      4.168320e-02   1.668660e-03 
     Pr-144m   U-235   Thermal   8.293280e-04   5.805270e-06 
     Pr-144m   U-235   Fast      7.971090e-04   1.115950e-05 
     Pr-144m   U-235   High      5.118870e-04   3.237970e-04 
     Pr-144m   U-238   Fast      6.876960e-04   9.627770e-06 
     Pr-144m   U-238   High      5.632870e-04   1.577200e-05 
     Pr-144m  Pu-239   Thermal   5.678530e-04   1.589980e-05 
     Pr-144m  Pu-239   Fast      5.596060e-04   1.566890e-05 
     Pr-144m  Pu-239   High      6.317290e-04   3.560480e-04 
     Pr-144m  Pu-241   Thermal   6.385790e-04   6.385790e-06 
     Pr-144m  Pu-241   Fast      6.295600e-04   3.777360e-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