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 --- ------------- --- ---------- ----------- ----------- ---------- ------- ----------- ----------- ----------- ---- 80 200 1 Total 5.70425E-12 5.70425E-12 5.7231E-12 1.00331 5.66871E+00 6.29877E+00 5.22072E+00 8037 80 200 2 Elastic 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 5.61096E+00 4.89981E+00 2.74392E+00 8037 80 200 4 Inelas 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.34901E+00 5.38997E-01 8037 80 200 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 4.05803E-03 1.93307E+00 8037 80 200 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.20528E-06 0.00000E+00 8037 80 200 102 n,gamma 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 5.77503E-02 4.59005E-02 2.13967E-03 8037 80 200 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.39173E-06 2.47866E-03 8037 80 200 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 4.11289E-08 1.96314E-05 8037 80 200 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.30694E-09 3.68548E-08 8037 80 200 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.30941E-16 6.57471E-20 8037 80 200 107 n,alpha 5.70425E-12 5.70425E-12 5.7231E-12 1.00331 1.48005E-11 9.80068E-08 9.10154E-05 8037 80 200 g 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.67176E-03 9.99271E-01 8037 80 200 * 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.38021E-03 9.33798E-01 8037 80 200 g 18 Fission 1.00000E-20 1.00000E-20 1.1284E-20 1.12838 1.22061E-19 1.00000E-20 1.00000E-20 8037 80 200 g 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.25388E-06 2.25854E-03 8037 80 200 * 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.37842E-07 2.20120E-04 8037 80 200 g 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.87451E-09 2.75516E-08 8037 80 200 * 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 4.32425E-10 9.30321E-09 8037