44-Ru-100



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)
     99.904214256 ± 0.000001129 (amu)  [mass excess = -89223.846 ± 1.052 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -3635.629 ± 18.124 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ru-100.
     Figures of cross sections, Ru-100:  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- 99 (Z= 44, A= 99), MT=102 (n,γ)
     Ru-100 (Z= 44, A=100), MT=  2 (Elastic scattering)
     Ru-100 (Z= 44, A=100), MT=  4 (Inelastic scattering)
     Ru-101 (Z= 44, A=101), MT= 16 (n,2n)
     Ru-102 (Z= 44, A=102), MT= 17 (n,3n)
     Rh-103 (Z= 45, A=103), MT= 33 (n,nt)
     Pd-102 (Z= 46, A=102), MT= 44 (n,n2p)
     Pd-102 (Z= 46, A=102), MT=106 (n,3He)
     Pd-102 (Z= 46, A=102), MT=115 (n,pd)
     Pd-104 (Z= 46, A=104), MT= 22 (n,nα)
     Pd-105 (Z= 46, A=105), 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-100    U-235   Thermal   2.116630e-12   1.354640e-12 
     Ru-100    U-235   Fast      7.245050e-13   4.636830e-13 
     Ru-100    U-235   High      6.879430e-09   4.402830e-09 
     Ru-100    U-238   Fast      1.640610e-14   1.049990e-14 
     Ru-100    U-238   High      1.101190e-11   7.047670e-12 
     Ru-100   Pu-239   Thermal   7.068880e-10   4.524080e-10 
     Ru-100   Pu-239   Fast      3.869370e-10   2.476400e-10 
     Ru-100   Pu-239   High      1.611040e-07   1.031070e-07 
     Ru-100   Pu-241   Thermal   2.420390e-12   1.549050e-12 
     Ru-100   Pu-241   Fast      1.918560e-12   1.227880e-12 
    -----------------------------------------------------------
    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-100    U-235   Thermal   5.581320e-08   3.572050e-08 
     Ru-100    U-235   Fast      2.365190e-08   1.513720e-08 
     Ru-100    U-235   High      8.608670e-06   5.503390e-06 
     Ru-100    U-238   Fast      1.560600e-09   9.984060e-10 
     Ru-100    U-238   High      1.131340e-07   7.232040e-08 
     Ru-100   Pu-239   Thermal   3.070220e-06   1.964780e-06 
     Ru-100   Pu-239   Fast      1.920080e-06   1.228780e-06 
     Ru-100   Pu-239   High      6.696440e-05   4.283520e-05 
     Ru-100   Pu-241   Thermal   7.971520e-08   5.100800e-08 
     Ru-100   Pu-241   Fast      4.906500e-08   3.140160e-08 
    -----------------------------------------------------------
    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