LLNL Evaluation, September 2005 1 0 0 0 5.413100+4 1.309051+2 -1 0 0 05446 1451 1 0.000000+0 0.000000+0 0 0 0 65446 1451 2 1.000000+0 2.000000+7 0 0 10 65446 1451 3 0.000000+0 0.000000+0 0 0 47 25446 1451 4 54-Xe-131 LLNL EVAL-Aug03 R. D. Hoffman, K. Kelley, et al. 5446 1451 5 DIST- REV- 5446 1451 6 LLNL Evaluation, September 2005 5446 1451 7 5446 1451 8 R. D. Hoffman, K. Kelley, F. S. Dietrich, R. Bauer, M. Mustafa, 5446 1451 9 D. Brown 5446 1451 10 5446 1451 11 ******************************************************************5446 1451 12 5446 1451 13 MF=3: CROSS SECTIONS FOR TARGET 131-XE (GS) 5446 1451 14 5446 1451 15 Cross sections to the ground state and any isomeric states in the 5446 1451 16 residual have been included for the following reactions: 5446 1451 17 5446 1451 18 (n,p) 5446 1451 19 5446 1451 20 Cross sections were calculated for incident energies from 5 keV 5446 1451 21 to 20 MeV, using the STAPRE code with a exiton model for 5446 1451 22 pre-equilibrium emission. Direct reaction contributions are not 5446 1451 23 included. 5446 1451 24 5446 1451 25 Exit particles considered are neutrons and protons only, with 5446 1451 26 transmission coefficients obtained from the optical potential of 5446 1451 27 Koning and Delaroche using the ECIS code. A simple Lorentzian is 5446 1451 28 assumed for the E1 photon strength function, and is normalized to 5446 1451 29 measured or systematic values of the average total s-wave 5446 1451 30 radiation width at the neutron binding energy. 5446 1451 31 5446 1451 32 Backshifted Fermi gas level density parameters are derived from 5446 1451 33 measured s-wave resonance spacings where available. For other 5446 1451 34 nuclei, systematic values are adopted. At low energies a constant 5446 1451 35 temperature form is adopted, and the two formulae are matched at 5446 1451 36 an energy between the backshift and the neutron binding energy so 5446 1451 37 as to give the best possible fit to known spectroscopic levels. 5446 1451 38 5446 1451 39 Discrete levels are taken from the Reference Input Parameter 5446 1451 40 Library (RIPL) with additional evaluations performed by R. Bauer. 5446 1451 41 5446 1451 42 Further details regarding this modeling effort can be found in R. 5446 1451 43 D. Hoffman, F. S. Dietrich, R. Bauer, K. Kelley, & M. Mustafa, 5446 1451 44 "Neutron and Charged- Particle Induced Cross Sections for 5446 1451 45 Radiochemistry in the Region of Iodine and Xenon", 2004, LLNL, 5446 1451 46 UCRL-TR-206721, available online at http://www.osti.gov/bridge 5446 1451 47 5446 1451 48 ******************************************************************5446 1451 49 5446 1451 50 *************************** DICTIONARY ***************************5446 1451 51 1 451 53 05446 1451 52 3 103 79 05446 1451 53 0.000000+0 0.000000+0 0 0 0 05446 1 099999 0.000000+0 0.000000+0 0 0 0 05446 0 0 0 5.413100+4 1.309051+2 0 0 0 05446 3103 1 -1.872300+5-1.872300+5 0 0 1 2285446 3103 2 228 2 5446 3103 3 1.886730+5 0.000000+0 1.910000+5 1.000000-9 2.000000+5 1.000100-95446 3103 4 2.090000+5 1.001000-9 2.190000+5 1.003100-9 2.300000+5 1.006700-95446 3103 5 2.410000+5 1.011700-9 2.520000+5 1.018100-9 2.640000+5 1.026600-95446 3103 6 2.760000+5 1.036700-9 2.890000+5 1.049500-9 3.030000+5 1.065200-95446 3103 7 3.170000+5 1.083100-9 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1.134800-2 1.400000+7 1.168400-25446 3103 59 1.410000+7 1.202400-2 1.420000+7 1.236800-2 1.430000+7 1.271300-25446 3103 60 1.440000+7 1.306000-2 1.450000+7 1.341200-2 1.460000+7 1.376500-25446 3103 61 1.470000+7 1.411800-2 1.480000+7 1.447300-2 1.490000+7 1.483200-25446 3103 62 1.500000+7 1.519000-2 1.510000+7 1.554800-2 1.520000+7 1.590500-25446 3103 63 1.530000+7 1.626200-2 1.540000+7 1.661900-2 1.550000+7 1.697700-25446 3103 64 1.560000+7 1.733300-2 1.570000+7 1.768500-2 1.580000+7 1.803600-25446 3103 65 1.590000+7 1.838600-2 1.600000+7 1.873400-2 1.610000+7 1.907700-25446 3103 66 1.620000+7 1.941700-2 1.630000+7 1.975500-2 1.640000+7 2.008900-25446 3103 67 1.650000+7 2.041700-2 1.660000+7 2.074100-2 1.670000+7 2.106200-25446 3103 68 1.680000+7 2.137800-2 1.690000+7 2.168600-2 1.700000+7 2.198900-25446 3103 69 1.710000+7 2.228800-2 1.720000+7 2.258100-2 1.730000+7 2.286600-25446 3103 70 1.740000+7 2.314500-2 1.750000+7 2.341700-2 1.760000+7 2.368300-25446 3103 71 1.770000+7 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