50-Sn-120



Spin
     Level energy(keV)   Spin & Parity       
     ----------------------------------------
       ground state      0+                    
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)
     119.902201634 ± 0.000000970 (amu)  [mass excess = -91098.591 ± 0.904 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -2680.608 ± 7.140 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Sn-120.
     Figures of cross sections, Sn-120:  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
     Sn-119 (Z= 50, A=119), MT=102 (n,γ)
     Sn-120 (Z= 50, A=120), MT=  2 (Elastic scattering)
     Sn-120 (Z= 50, A=120), MT=  4 (Inelastic scattering)
     Sn-122 (Z= 50, A=122), MT= 17 (n,3n)
     Sb-121 (Z= 51, A=121), MT= 28 (n,np)
     Sb-121 (Z= 51, A=121), MT=104 (n,d)
     Te-122 (Z= 52, A=122), MT=106 (n,3He)
     Te-123 (Z= 52, A=123), MT=107 (n,α)
     Te-124 (Z= 52, A=124), 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)
    -----------------------------------------------------------
     Sn-120    U-235   Thermal   2.995230e-08   1.916940e-08 
     Sn-120    U-235   Fast      8.861700e-08   5.671490e-08 
     Sn-120    U-235   High      4.245820e-06   2.717320e-06 
     Sn-120    U-238   Fast      1.290480e-09   8.259080e-10 
     Sn-120    U-238   High      6.497080e-08   4.158130e-08 
     Sn-120   Pu-239   Thermal   7.278850e-07   4.658460e-07 
     Sn-120   Pu-239   Fast      1.509750e-06   9.662440e-07 
     Sn-120   Pu-239   High      7.439820e-05   4.761490e-05 
     Sn-120   Pu-241   Thermal   1.950320e-08   1.248200e-08 
     Sn-120   Pu-241   Fast      9.702700e-08   6.209730e-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)
    -----------------------------------------------------------
     Sn-120    U-235   Thermal   1.280100e-04   1.026930e-05 
     Sn-120    U-235   Fast      3.557360e-04   2.837380e-05 
     Sn-120    U-235   High      1.105680e-02   1.209160e-03 
     Sn-120    U-238   Fast      3.878110e-04   4.259000e-05 
     Sn-120    U-238   High      7.797090e-03   8.554660e-04 
     Sn-120   Pu-239   Thermal   3.165260e-04   3.529750e-05 
     Sn-120   Pu-239   Fast      5.771490e-04   6.452080e-05 
     Sn-120   Pu-239   High      1.311890e-02   1.514110e-03 
     Sn-120   Pu-241   Thermal   2.581870e-04   5.896540e-05 
     Sn-120   Pu-241   Fast      8.708610e-04   1.385300e-04 
    -----------------------------------------------------------
    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