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 --- ------------- --- ---------- ----------- ----------- ---------- ------- ----------- ----------- ----------- ---- 76 186 1 Total 9.78766E-05 9.78766E-05 9.8134E-05 1.00263 4.68104E+01 7.22278E+00 5.31109E+00 7631 76 186 2 Elastic 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 4.53897E+01 4.40365E+00 2.65932E+00 7631 76 186 4 Inelas 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.75246E+00 5.75483E-01 7631 76 186 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 5.48867E-03 2.06771E+00 7631 76 186 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.09251E-05 0.00000E+00 7631 76 186 102 n,gamma 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 1.42047E+00 6.11659E-02 1.21733E-03 7631 76 186 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.91261E-06 4.90803E-03 7631 76 186 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.71337E-07 2.52110E-04 7631 76 186 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.45019E-08 3.75252E-06 7631 76 186 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.43936E-13 1.23599E-13 7631 76 186 107 n,alpha 9.78766E-05 9.78766E-05 9.8134E-05 1.00263 2.48957E-04 3.79329E-06 1.98085E-03 7631 76 186 g 18 Fission 1.00000E-20 1.00000E-20 1.1284E-20 1.12838 1.22061E-19 1.00000E-20 1.00000E-20 7631 76 186 g 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.45009E-06 4.14633E-03 7631 76 186 * 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 4.62523E-07 7.61705E-04 7631 76 186 g 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.08655E-08 3.14371E-06 7631 76 186 * 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.63643E-09 6.08807E-07 7631