PROGRAM INTER VERSION 8.08
                             --------------------------

 Selected Integrations of ENDF File 3 and File 10 Cross Sections

 Thermal cross section : Sig(2200) = Sig(Eth)
 Thermal energy        : Eth=  2.53000E-02 (eV)

 Ezero cross section   : Sig(Ezero)
 Ezero energy (input)  : E0 =  2.53000E-02 (eV)

 Maxwellian average    : Avg-Sigma = (2/sqrt(Pi)) Intg[E1:E2] Sig(E) Phi_m(E) dE / Intg[E1:E2] Phi_m(E) dE
 Maxwellian spectrum   : Phi_m(E)  = (E/E0^2) exp(-E/E0)
 Spectrum Temperature  : E0 =  2.53000E-02 (eV)
 Integration Limits    : E1 =  1.00000E-05 (eV)  E2 =  1.00000E+01 (eV)
 Integral of Spectrum       =  1.00000E+00

 Westcott g-factor     : G-fact = 2/sqrt(Pi)  Avg-Sigma / Sig(2200)

 Resonance Integral    : Res.Integ = Intg[E3:E4] Sig(E)/E dE
 Integration Limits    : E3 =  5.00000E-01 (eV)  E4 =  1.00000E+05 (eV)
 Integral of Spectrum       =  1.22061E+01

 Fiss.spect. average   : Sig(Fiss) = Intg[E1:E2] Sig(E) Phi_f(E) dE / Intg[E1:E2] Phi_f(E) dE
 Fission spectrum      : Phi_f(E)  = sqrt(E/Ef)/Ef exp(-E/E0)
 Spectrum Temperature  : Ef =  1.35000E+06 (eV)
 Integration Limits    : E1 =  1.00000E+03 (eV)  E2 =  2.00000E+07 (eV)
 Integral of Spectrum       =  1.00000E+00

 E14 cross-section     : Sig(E14)
 Selected Energy       : E14 =  1.40000E+07 eV


   Z   A LISO  LFS  MT  Reaction    Sig(2200)   Sig(Ezero)  Avg-Sigma  G-fact   Res Integ   Sig(Fiss)    Sig(E14)   MAT
 --- ------------- ---  ---------- ----------- ----------- ---------- -------  ----------- ----------- ----------- ----
  90 233             1  Total      1.31700E+03 1.31700E+03 1.3224E+03 1.00413  1.19989E+03 7.64498E+00 5.86897E+00 9043
  90 233             2  Elastic    1.20000E+01 1.20000E+01 2.3502E+01 1.95853  2.20086E+02 4.37680E+00 2.76831E+00 9043
  90 233             4  Inelas     0.00000E+00 0.00000E+00 0.0000E+00 0.00000  7.39825E-01 3.03126E+00 4.08216E-01 9043
  90 233            16  n,2n       0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 7.42987E-02 1.60312E+00 9043
  90 233            17  n,3n       0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 2.12480E-04 6.87983E-01 9043
  90 233            18  Fission    1.50000E+01 1.50000E+01 2.3586E+01 1.57240  1.17788E+02 1.00823E-01 4.00213E-01 9043
  90 233           102  n,gamma    1.29000E+03 1.29000E+03 2.0304E+03 1.57394  8.57818E+02 6.00515E-02 1.12513E-03 9043