44-Ru-102



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)
     101.904344096 ± 0.000001155 (amu)  [mass excess = -89102.900 ± 1.076 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -2322.473 ± 4.561 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ru-102.
     Figures of cross sections, Ru-102:  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
     Ru-101 (Z= 44, A=101), MT=102 (n,γ)
     Ru-102 (Z= 44, A=102), MT=  2 (Elastic scattering)
     Ru-102 (Z= 44, A=102), MT=  4 (Inelastic scattering)
     Ru-103 (Z= 44, A=103), MT= 16 (n,2n)
     Ru-104 (Z= 44, A=104), MT= 17 (n,3n)
     Rh-103 (Z= 45, A=103), MT= 28 (n,np)
     Rh-103 (Z= 45, A=103), MT=104 (n,d)
     Rh-105 (Z= 45, A=105), MT= 33 (n,nt)
     Pd-104 (Z= 46, A=104), MT=106 (n,3He)
     Pd-105 (Z= 46, A=105), MT=107 (n,α)
     Pd-106 (Z= 46, A=106), MT= 22 (n,nα)
     Pd-107 (Z= 46, A=107), 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)
    -----------------------------------------------------------
     Ru-102    U-235   Thermal   9.744480e-09   6.236470e-09 
     Ru-102    U-235   Fast      3.951850e-09   2.529180e-09 
     Ru-102    U-235   High      1.592180e-06   1.018990e-06 
     Ru-102    U-238   Fast      1.620600e-10   1.037190e-10 
     Ru-102    U-238   High      1.311430e-08   8.393140e-09 
     Ru-102   Pu-239   Thermal   7.648800e-07   4.895230e-07 
     Ru-102   Pu-239   Fast      6.918880e-07   4.428080e-07 
     Ru-102   Pu-239   High      2.540650e-05   1.626010e-05 
     Ru-102   Pu-241   Thermal   1.040170e-08   6.657070e-09 
     Ru-102   Pu-241   Fast      1.309020e-08   8.377700e-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)
    -----------------------------------------------------------
     Ru-102    U-235   Thermal   4.276280e-02   4.837370e-04 
     Ru-102    U-235   Fast      4.348290e-02   4.489570e-04 
     Ru-102    U-235   High      3.257700e-02   3.579250e-03 
     Ru-102    U-238   Fast      6.442770e-02   6.463950e-04 
     Ru-102    U-238   High      4.623010e-02   3.697370e-03 
     Ru-102   Pu-239   Thermal   6.125080e-02   8.577590e-04 
     Ru-102   Pu-239   Fast      6.729970e-02   6.734170e-04 
     Ru-102   Pu-239   High      5.479470e-02   6.024410e-03 
     Ru-102   Pu-241   Thermal   6.653260e-02   1.331200e-03 
     Ru-102   Pu-241   Fast      6.856960e-02   9.650610e-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