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
 --- ------------- ---  ---------- ----------- ----------- ---------- -------  ----------- ----------- ----------- ----
  80 202             1  Total      3.85354E-13 3.85354E-13 3.8663E-13 1.00331  1.41667E+00 6.30410E+00 5.26999E+00 8043
  80 202             2  Elastic    0.00000E+00 0.00000E+00 0.0000E+00 0.00000  1.41256E+00 4.81026E+00 2.72539E+00 8043
  80 202             4  Inelas     0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 1.47894E+00 3.58884E-01 8043
  80 202            16  n,2n       0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 6.25776E-03 2.18346E+00 8043
  80 202            17  n,3n       0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 1.28029E-05 0.00000E+00 8043
  80 202           102  n,gamma    0.00000E+00 0.00000E+00 0.0000E+00 0.00000  4.10930E-03 8.63335E-03 1.26628E-03 8043
  80 202           103  n,p        0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 5.19776E-07 9.48260E-04 8043
  80 202           104  n,d        0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 2.62273E-08 6.07303E-06 8043
  80 202           105  n,t        0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 2.10306E-09 3.31402E-08 8043
  80 202           106  n,He3      0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 2.23574E-17 1.72931E-20 8043
  80 202           107  n,alpha    3.85354E-13 3.85354E-13 3.8663E-13 1.00331  2.03932E-13 2.90665E-08 3.49882E-05 8043
  80 202        g   18  Fission    1.00000E-20 1.00000E-20 1.1284E-20 1.12838  1.22061E-19 1.00000E-20 1.00000E-20 8043
  80 202        g  105  n,t        0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 1.80779E-09 3.10728E-08 8043
  80 202        *  105  n,t        0.00000E+00 0.00000E+00 0.0000E+00 0.00000  0.00000E+00 2.95271E-10 2.06736E-09 8043