44-Ru-104



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)
     103.905427481 ± 0.000002755 (amu)  [mass excess = -88093.734 ± 2.567 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -1138.042 ± 3.337 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ru-104.
     Figures of cross sections, Ru-104:  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-103 (Z= 44, A=103), MT=102 (n,γ)
     Ru-104 (Z= 44, A=104), MT=  2 (Elastic scattering)
     Ru-104 (Z= 44, A=104), MT=  4 (Inelastic scattering)
     Ru-105 (Z= 44, A=105), MT= 16 (n,2n)
     Ru-106 (Z= 44, A=106), MT= 17 (n,3n)
     Rh-105 (Z= 45, A=105), MT= 28 (n,np)
     Rh-105 (Z= 45, A=105), MT=104 (n,d)
     Pd-105 (Z= 46, A=105), MT=111 (n,2p)
     Pd-106 (Z= 46, A=106), MT=106 (n,3He)
     Pd-107 (Z= 46, A=107), MT=107 (n,α)
     Pd-108 (Z= 46, A=108), 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)
    -----------------------------------------------------------
     Ru-104    U-235   Thermal   3.264800e-06   2.089470e-06 
     Ru-104    U-235   Fast      1.586730e-06   1.015500e-06 
     Ru-104    U-235   High      5.049920e-05   3.231950e-05 
     Ru-104    U-238   Fast      2.010750e-07   1.286880e-07 
     Ru-104    U-238   High      3.043310e-06   1.947720e-06 
     Ru-104   Pu-239   Thermal   2.440320e-04   1.561800e-04 
     Ru-104   Pu-239   Fast      1.520950e-04   9.734100e-05 
     Ru-104   Pu-239   High      1.139410e-03   7.292220e-04 
     Ru-104   Pu-241   Thermal   8.431360e-06   5.396070e-06 
     Ru-104   Pu-241   Fast      1.242070e-05   7.949220e-06 
    -----------------------------------------------------------
    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-104    U-235   Thermal   1.879840e-02   1.882590e-04 
     Ru-104    U-235   Fast      2.070890e-02   2.077550e-04 
     Ru-104    U-235   High      2.488460e-02   3.967390e-03 
     Ru-104    U-238   Fast      5.066100e-02   5.866600e-04 
     Ru-104    U-238   High      4.049740e-02   1.627700e-03 
     Ru-104   Pu-239   Thermal   6.099780e-02   6.115440e-04 
     Ru-104   Pu-239   Fast      6.586920e-02   4.615040e-04 
     Ru-104   Pu-239   High      5.447060e-02   5.986760e-03 
     Ru-104   Pu-241   Thermal   7.196080e-02   1.445430e-03 
     Ru-104   Pu-241   Fast      7.316930e-02   1.028270e-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