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 --- ------------- --- ---------- ----------- ----------- ---------- ------- ----------- ----------- ----------- ---- 80 201 1 Total 1.11492E-09 1.11492E-09 1.1175E-09 1.00234 8.99026E+01 6.41171E+00 5.23496E+00 8040 80 201 2 Elastic 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 8.15550E+01 4.67456E+00 2.75313E+00 8040 80 201 4 Inelas 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 1.66503E+00 1.68411E+00 3.30380E-01 8040 80 201 16 n,2n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.31845E-02 2.14705E+00 8040 80 201 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.28376E-05 0.00000E+00 8040 80 201 102 n,gamma 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 6.72968E+00 3.98099E-02 1.44998E-03 8040 80 201 103 n,p 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.80306E-06 2.79593E-03 8040 80 201 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 3.28792E-08 1.62693E-05 8040 80 201 105 n,t 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.03000E-08 2.24060E-06 8040 80 201 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 6.56217E-16 2.38251E-20 8040 80 201 107 n,alpha 1.11492E-09 1.11492E-09 1.1175E-09 1.00234 9.32797E-09 1.12308E-07 1.32830E-04 8040 80 201 g 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 6.42847E-06 0.00000E+00 8040 80 201 * 17 n,3n 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 6.40615E-06 0.00000E+00 8040 80 201 g 18 Fission 1.00000E-20 1.00000E-20 1.1284E-20 1.12838 1.22061E-19 1.00000E-20 1.00000E-20 8040 80 201 g 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 2.86672E-08 1.49466E-05 8040 80 201 * 104 n,d 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 4.21194E-09 1.32266E-06 8040 80 201 g 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 5.54013E-16 2.21737E-20 8040 80 201 * 106 n,He3 0.00000E+00 0.00000E+00 0.0000E+00 0.00000 0.00000E+00 1.02204E-16 0.00000E+00 8040