44-Ru-101



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)
     100.905576872 ± 0.000001154 (amu)  [mass excess = -87954.577 ± 1.075 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -543.751 ± 5.922 (keV) 
Strong Gamma-rays from Decay of Ru-101 (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 
  ----------------------------------------------------------
        220.7            82.71         IT 
        306.6            98.46         IT 
  ----------------------------------------------------------
     *: relative, ~ approximate, ? calculated or estimatted 
     >: greater than or equal to, <: less than or equal to  
  [ Intensities; total intensity of the nuclide is 100(%). ]
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ru-101.
     Figures of cross sections, Ru-101:  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-100 (Z= 44, A=100), MT=102 (n,γ)
     Ru-101 (Z= 44, A=101), MT=  2 (Elastic scattering)
     Ru-101 (Z= 44, A=101), MT=  4 (Inelastic scattering)
     Ru-102 (Z= 44, A=102), MT= 16 (n,2n)
     Ru-103 (Z= 44, A=103), MT= 17 (n,3n)
     Rh-103 (Z= 45, A=103), MT= 32 (n,nd)
     Rh-103 (Z= 45, A=103), MT=105 (n,t)
     Pd-102 (Z= 46, A=102), MT=111 (n,2p)
     Pd-104 (Z= 46, A=104), MT=107 (n,α)
     Pd-105 (Z= 46, A=105), 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-101    U-235   Thermal   1.617430e-10   1.035150e-10 
     Ru-101    U-235   Fast      6.396790e-11   4.093940e-11 
     Ru-101    U-235   High      1.191640e-07   7.626460e-08 
     Ru-101    U-238   Fast      1.870700e-12   1.197250e-12 
     Ru-101    U-238   High      5.566060e-10   3.562280e-10 
     Ru-101   Pu-239   Thermal   2.429620e-08   1.554950e-08 
     Ru-101   Pu-239   Fast      2.039670e-08   1.305390e-08 
     Ru-101   Pu-239   High      2.271470e-06   1.453740e-06 
     Ru-101   Pu-241   Thermal   2.020330e-10   1.293010e-10 
     Ru-101   Pu-241   Fast      1.808640e-10   1.157530e-10 
    -----------------------------------------------------------
    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-101    U-235   Thermal   5.175190e-02   5.179280e-04 
     Ru-101    U-235   Fast      5.110900e-02   7.297080e-04 
     Ru-101    U-235   High      3.456630e-02   3.797800e-03 
     Ru-101    U-238   Fast      6.212920e-02   8.701270e-04 
     Ru-101    U-238   High      5.700860e-02   1.595680e-03 
     Ru-101   Pu-239   Thermal   6.016950e-02   8.429490e-04 
     Ru-101   Pu-239   Fast      6.667540e-02   6.673490e-04 
     Ru-101   Pu-239   High      5.000230e-02   5.497400e-03 
     Ru-101   Pu-241   Thermal   6.231090e-02   1.246420e-03 
     Ru-101   Pu-241   Fast      6.482910e-02   9.122410e-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