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
 --- ------------- ---  ---------- ----------- ----------- ---------- -------  ----------- ----------- ----------- ----
  92 239             1  Total      0.00000E+00 0.00000E+00 0.0000E+00 0.00000  3.09535E+01 7.64030E+00 5.80806E+00 9240
  92 239             2  Elastic    0.00000E+00 0.00000E+00 0.0000E+00 0.00000  2.72193E+01 4.48755E+00 2.92026E+00 9240
  92 239             4  Inelas     0.00000E+00 0.00000E+00 0.0000E+00 0.00000  1.91567E-01 2.60615E+00 3.72985E-01 9240
  92 239            16  n,2n       0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 7.31979E-02 1.05372E+00 9240
  92 239            17  n,3n       0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 1.46893E-04 4.53793E-01 9240
  92 239            18  Fission    0.00000E+00 0.00000E+00 0.0000E+00 0.00000  1.37576E+00 3.79199E-01 9.06469E-01 9240
  92 239           102  n,gamma    0.00000E+00 0.00000E+00 0.0000E+00 0.00000  2.14525E+00 8.59408E-02 1.43224E-03 9240