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 --- ------------- --- ---------- ----------- ----------- ---------- ------- ----------- ----------- ----------- ---- 80 198 1 Total 1.31308E-09 1.31308E-09 1.3172E-09 1.00315 2.57254E+01 6.38770E+00 5.19508E+00 8031 80 198 2 Elastic 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 2.53123E+01 4.99054E+00 2.72555E+00 8031 80 198 4 Inelas 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.29560E+00 4.56216E-01 8031 80 198 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.71518E-03 2.00702E+00 8031 80 198 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.73944E-06 0.00000E+00 8031 80 198 102 n,gamma 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 4.13127E-01 9.78334E-02 1.86133E-03 8031 80 198 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.00409E-06 4.07019E-03 8031 80 198 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 7.50837E-08 5.52328E-05 8031 80 198 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.03709E-09 8.09820E-08 8031 80 198 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 8.59615E-15 1.84422E-17 8031 80 198 107 n,alpha 1.31308E-09 1.31308E-09 1.3172E-09 1.00315 1.28209E-08 3.63101E-07 2.66716E-04 8031 80 198 g 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.05134E-03 8.56857E-01 8031 80 198 * 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.65716E-03 1.15016E+00 8031 80 198 g 18 Fission 1.00000E-20 1.00000E-20 1.1284E-20 1.12838 1.22061E-19 1.00000E-20 1.00000E-20 8031 80 198 g 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.75332E-06 3.78460E-03 8031 80 198 * 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.50765E-07 2.85589E-04 8031 80 198 g 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.89470E-08 3.27745E-05 8031 80 198 * 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.61367E-08 2.24582E-05 8031 80 198 g 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.24459E-09 4.36533E-08 8031 80 198 * 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.45135E-09 2.30975E-08 8031 80 198 * 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.41155E-10 1.42312E-08 8031