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 --- ------------- --- ---------- ----------- ----------- ---------- ------- ----------- ----------- ----------- ---- 78 196 1 Total 2.46074E-12 2.46074E-12 2.4681E-12 1.00299 2.28417E+01 6.46797E+00 5.20594E+00 7843 78 196 2 Elastic 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 2.25762E+01 5.00762E+00 2.76250E+00 7843 78 196 4 Inelas 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.41265E+00 3.90498E-01 7843 78 196 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 5.59712E-03 2.05085E+00 7843 78 196 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.15194E-05 0.00000E+00 7843 78 196 102 n,gamma 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 2.65506E-01 4.20937E-02 1.22718E-03 7843 78 196 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.62035E-07 6.56513E-04 7843 78 196 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.40480E-08 8.03673E-06 7843 78 196 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.05967E-09 4.28222E-08 7843 78 196 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.80878E-16 2.18587E-20 7843 78 196 107 n,alpha 2.46074E-12 2.46074E-12 2.4681E-12 1.00299 2.33561E-11 1.38614E-07 1.90646E-04 7843 78 196 g 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.19785E-03 9.10148E-01 7843 78 196 * 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.38579E-03 1.14071E+00 7843 78 196 g 18 Fission 1.00000E-20 1.00000E-20 1.1284E-20 1.12838 1.22061E-19 3.62606E-18 1.00000E-20 7843 78 196 g 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.41888E-07 6.18974E-04 7843 78 196 * 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.01472E-08 3.75394E-05 7843 78 196 g 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.45750E-08 5.96816E-06 7843 78 196 n 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 9.47303E-09 2.06857E-06 7843 78 196 g 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.03815E-09 4.27830E-08 7843