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
 --- ------------- ---  ---------- ----------- ----------- ---------- -------  ----------- ----------- ----------- ----
  92 240             1  Total      0.00000E+00 0.00000E+00 0.0000E+00 0.00000  3.18239E+01 8.06479E+00 5.83867E+00 9243
  92 240             2  Elastic    0.00000E+00 0.00000E+00 0.0000E+00 0.00000  3.07805E+01 5.02525E+00 2.72189E+00 9243
  92 240             4  Inelas     0.00000E+00 0.00000E+00 0.0000E+00 0.00000  2.29308E-01 2.77752E+00 6.21052E-01 9243
  92 240            16  n,2n       0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 2.44742E-02 8.48820E-01 9243
  92 240            17  n,3n       0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 3.33426E-04 9.22054E-01 9243
  92 240            18  Fission    0.00000E+00 0.00000E+00 0.0000E+00 0.00000  1.23841E-05 1.88871E-01 7.23686E-01 9243
  92 240           102  n,gamma    0.00000E+00 0.00000E+00 0.0000E+00 0.00000  8.14037E-01 4.83392E-02 1.17470E-03 9243