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 --- ------------- --- ---------- ----------- ----------- ---------- ------- ----------- ----------- ----------- ---- 76 188 1 Total 2.97545E-05 2.97545E-05 2.9836E-05 1.00274 3.98436E+01 7.09606E+00 5.32472E+00 7637 76 188 2 Elastic 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 3.91370E+01 4.30534E+00 2.67985E+00 7637 76 188 4 Inelas 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.74673E+00 5.43948E-01 7637 76 188 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 7.49520E-03 2.09567E+00 7637 76 188 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.87350E-05 0.00000E+00 7637 76 188 102 n,gamma 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 7.06563E-01 3.64689E-02 1.27060E-03 7637 76 188 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.84713E-06 2.84719E-03 7637 76 188 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.04725E-07 1.03938E-04 7637 76 188 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 9.59903E-09 1.66942E-06 7637 76 188 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 8.61704E-15 3.92094E-18 7637 76 188 107 n,alpha 2.97545E-05 2.97545E-05 2.9836E-05 1.00274 1.49615E-05 1.48888E-06 9.23612E-04 7637 76 188 g 18 Fission 1.00000E-20 1.00000E-20 1.1284E-20 1.12838 1.22061E-19 1.00000E-20 1.00000E-20 7637 76 188 g 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.36074E-06 2.01017E-03 7637 76 188 * 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 4.86388E-07 8.37025E-04 7637 76 188 g 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 7.29911E-09 1.45150E-06 7637 76 188 * 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.29992E-09 2.17926E-07 7637