59-Pr-141



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)
     140.907657568 ± 0.000002292 (amu)  [mass excess = -86016.422 ± 2.135 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1823.014 ± 2.809 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Pr-141.
     Figures of cross sections, Pr-141:  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
     Pr-141 (Z= 59, A=141), MT=  2 (Elastic scattering)
     Pr-141 (Z= 59, A=141), MT=  4 (Inelastic scattering)
     Pr-143 (Z= 59, A=143), MT= 17 (n,3n)
     Nd-142 (Z= 60, A=142), MT= 28 (n,np)
     Nd-142 (Z= 60, A=142), MT=104 (n,d)
     Nd-143 (Z= 60, A=143), MT= 32 (n,nd)
     Nd-143 (Z= 60, A=143), MT= 41 (n,2np)
     Nd-143 (Z= 60, A=143), MT=105 (n,t)
     Nd-144 (Z= 60, A=144), MT= 33 (n,nt)
     Pm-147 (Z= 61, A=147), MT= 25 (n,3nα)

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-141    U-235   Thermal   4.682550e-13   2.996830e-13 
     Pr-141    U-235   Fast      1.776330e-13   1.136850e-13 
     Pr-141    U-235   High      1.712350e-08   1.095910e-08 
     Pr-141    U-238   High      1.101190e-11   7.047670e-12 
     Pr-141   Pu-239   Thermal   2.529600e-10   1.618940e-10 
     Pr-141   Pu-239   Fast      2.609570e-10   1.670130e-10 
     Pr-141   Pu-239   High      4.933200e-07   3.157250e-07 
     Pr-141   Pu-241   Thermal   3.000490e-13   1.920310e-13 
     Pr-141   Pu-241   Fast      6.235310e-13   3.990600e-13 
    -----------------------------------------------------------
    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-141    U-235   Thermal   5.838400e-02   5.909730e-04 
     Pr-141    U-235   Fast      5.937240e-02   8.412380e-04 
     Pr-141    U-235   High      4.492490e-02   1.795560e-03 
     Pr-141    U-238   Fast      5.337390e-02   8.530910e-06 
     Pr-141    U-238   High      4.386260e-02   8.775730e-04 
     Pr-141   Pu-239   Thermal   5.246490e-02   1.049390e-03 
     Pr-141   Pu-239   Fast      5.146670e-02   1.441190e-03 
     Pr-141   Pu-239   High      3.562690e-02   2.136270e-03 
     Pr-141   Pu-241   Thermal   4.906770e-02   6.868810e-04 
     Pr-141   Pu-241   Fast      5.071770e-02   2.030440e-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