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 --- ------------- --- ---------- ----------- ----------- ---------- ------- ----------- ----------- ----------- ---- 84 209 1 Total 3.71871E-01 3.71871E-01 3.7289E-01 1.00274 3.33163E+01 6.38333E+00 5.26819E+00 8434 84 209 2 Elastic 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 3.30726E+01 5.06931E+00 2.72007E+00 8434 84 209 4 Inelas 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.29932E+00 2.94260E-01 8434 84 209 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 8.84707E-03 2.23080E+00 8434 84 209 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 5.99206E-06 0.00000E+00 8434 84 209 102 n,gamma 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 5.96059E-02 4.94547E-03 1.54083E-03 8434 84 209 103 n,p 1.74999E-07 1.74999E-07 1.7548E-07 1.00274 8.97238E-08 5.81495E-05 1.24969E-02 8434 84 209 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 4.58922E-07 9.83314E-04 8434 84 209 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.75814E-08 3.23218E-05 8434 84 209 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 5.56163E-12 2.50523E-10 8434 84 209 107 n,alpha 3.71871E-01 3.71871E-01 3.7289E-01 1.00274 1.83860E-01 4.90655E-04 3.07811E-03 8434 84 209 g 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 5.56408E-06 0.00000E+00 8434 84 209 * 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 4.26207E-07 0.00000E+00 8434 84 209 g 18 Fission 1.00000E-20 1.00000E-20 1.1284E-20 1.12838 1.22061E-19 5.55067E-16 1.00000E-20 8434 84 209 g 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.45031E-12 1.73623E-10 8434 84 209 * 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.11132E-12 7.68996E-11 8434