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 --- ------------- --- ---------- ----------- ----------- ---------- ------- ----------- ----------- ----------- ---- 72 181 1 Total 2.49604E-06 2.49604E-06 2.5012E-06 1.00206 2.47055E+02 7.10536E+00 5.15773E+00 7246 72 181 2 Elastic 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 2.31785E+02 5.09650E+00 2.79854E+00 7246 72 181 4 Inelas 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 5.20216E-01 1.92539E+00 2.08120E-01 7246 72 181 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.73254E-02 2.03873E+00 7246 72 181 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 7.49088E-05 1.08198E-01 7246 72 181 102 n,gamma 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 1.47494E+01 4.60786E-02 1.37911E-03 7246 72 181 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.61592E-06 2.40429E-03 7246 72 181 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 6.32434E-08 4.08879E-05 7246 72 181 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.29518E-08 3.16501E-06 7246 72 181 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.70366E-16 3.03414E-20 7246 72 181 107 n,alpha 2.49604E-06 2.49604E-06 2.5012E-06 1.00206 1.05455E-05 2.30789E-07 2.83685E-04 7246 72 181 g 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.65487E-02 1.84278E+00 7246 72 181 * 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 7.76083E-04 1.95944E-01 7246 72 181 g 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 6.70476E-05 1.03675E-01 7246 72 181 * 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 6.56458E-06 4.52339E-03 7246 72 181 * 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.28795E-06 0.00000E+00 7246 72 181 g 18 Fission 1.00000E-20 1.00000E-20 1.1284E-20 1.12838 1.22061E-19 1.00000E-20 1.00000E-20 7246