42-Mo-97



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)
     96.906018118 ± 0.000000490 (amu)  [mass excess = -87543.559 ± 0.457 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     -324.708 ± 3.744 (keV) 
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Mo-97.
     Figures of cross sections, Mo-97:  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
     Mo- 96 (Z= 42, A= 96), MT=102 (n,γ)
     Mo- 97 (Z= 42, A= 97), MT=  2 (Elastic scattering)
     Mo- 97 (Z= 42, A= 97), MT=  4 (Inelastic scattering)
     Mo- 98 (Z= 42, A= 98), MT= 16 (n,2n)
     Mo- 99 (Z= 42, A= 99), MT= 17 (n,3n)
     Tc- 99 (Z= 43, A= 99), MT= 32 (n,nd)
     Tc- 99 (Z= 43, A= 99), MT=105 (n,t)
     Ru- 98 (Z= 44, A= 98), MT=111 (n,2p)
     Ru- 99 (Z= 44, A= 99), MT=106 (n,3He)
     Ru-100 (Z= 44, A=100), MT=107 (n,α)
     Ru-101 (Z= 44, A=101), MT= 22 (n,nα)
     Pd-104 (Z= 46, A=104), MT=108 (n,2α)

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)
    -----------------------------------------------------------
     Mo- 97    U-235   Thermal   2.486040e-08   1.591070e-08 
     Mo- 97    U-235   Fast      9.919520e-09   6.348490e-09 
     Mo- 97    U-235   High      4.245820e-06   2.717320e-06 
     Mo- 97    U-238   Fast      3.101160e-10   1.984740e-10 
     Mo- 97    U-238   High      3.694030e-08   2.364170e-08 
     Mo- 97   Pu-239   Thermal   1.039840e-06   6.654950e-07 
     Mo- 97   Pu-239   Fast      6.828890e-07   4.370490e-07 
     Mo- 97   Pu-239   High      2.121380e-05   1.357680e-05 
     Mo- 97   Pu-241   Thermal   2.180350e-08   1.395430e-08 
     Mo- 97   Pu-241   Fast      1.458900e-08   9.336980e-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)
    -----------------------------------------------------------
     Mo- 97    U-235   Thermal   6.044680e-02   6.367340e-04 
     Mo- 97    U-235   Fast      6.063670e-02   6.781530e-04 
     Mo- 97    U-235   High      5.593210e-02   3.392540e-03 
     Mo- 97    U-238   Fast      5.648640e-02   9.452880e-04 
     Mo- 97    U-238   High      5.374530e-02   1.199660e-03 
     Mo- 97   Pu-239   Thermal   5.473240e-02   8.021660e-04 
     Mo- 97   Pu-239   Fast      5.349980e-02   5.906670e-04 
     Mo- 97   Pu-239   High      4.612250e-02   1.887590e-03 
     Mo- 97   Pu-241   Thermal   4.874680e-02   9.915470e-04 
     Mo- 97   Pu-241   Fast      4.521480e-02   1.090790e-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