Calculate Cross Sections from Resonance Parameters (RECENT 2000-1) ============================================================================== Retrieval Criteria----------- MAT File 2 Mimimum Cross Section- 1.00000-10 Reactions with No Background- Output (Resonance Contribution) Calculate/Edit Mode---------- Calculate. List Resonance ParameterS. Negative Cross Sections------ Make = 0 (No Negative Output) Monitor Mode----------------- On ============================================================================== ENDF/B Input and Output Data Filenames ENDF.IN RECENT.OUT ============================================================================== Requested MAT Ranges ============================================================================== Mimimum Maximum ============================================================================== 1 9999 ============================================================================== Allowable Uncertainty ============================================================================== Energy Uncertainty per-cent ============================================================================== 0.0 1.000000-2 1.000 ============================================================================== ENDF/B Tape Label ============================================================================== ENDF/B-VII submitted 03/2005 1 ****************************************************************************** Processing 82-Pb-207 MAT= 8234 ****************************************************************************** Based on the Format and Contents of MF=1, MT=451 (1) ENDF/B-VI Format. (2) Material is NOT Fissile (LFI=0). (3) Resonance Parameters are Given (LRP=1). (4) Projectile ZA = 1 (Neutron). (5) Temperature of Background 0.0 Kelvin. ============================================================================== Listing of All Resonance Parameters ============================================================================== Element or Material------------------ 82-Pb-207 Atomic Weight Ratio------------------ 2.052000+2 Number of Isotopes------------------- 1 ============================================================================== Isotope Number----------------------- 1 Isotope------------------------------ 82-Pb-207 Fractional Abundance----------------- 1.000000+0 LFW (Fission Widths)----------------- 0 (No Fission Widths) Number of Energy Ranges-------------- 1 ============================================================================== Lower Limit of the Energy Range------ 1.000000-5 eV Upper Limit of the Energy Range------ 475000.000 eV LRU (Type of Region)----------------- 1 (Resolved Region) LRF (Type of Resolved Parameters)---- 3 (Reich-Moore) NRO (Scattering Radius)-------------- 0 (Energy Independent) NAPS (Channel Radius)---------------- 1 (= Scattering Radius) ============================================================================== Nuclear Spin of Target--------------- 5.000000-1 Scattering Radius-------------------- 9.500000-1 Number of L Values------------------- 3 ============================================================================== Atomic Weight Ratio of Isotope------- 2.052000+2 L Dependent Scattering Radius-------- 0.0 Angular Momentum (L)----------------- 0 Number of Resonances----------------- 16 WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING L Dependent Scattering Radius in the Evaluation is Zero. Have Defined it to be Equal to the Scattering Radius. (see, ENDF/B-VI Formats and Procedures Manual, page 2.11) ============================================================================== Reich-Moore Resonance Parameters ============================================================================== Energy J Value Neutron Capture Fission-1 Fission-2 (eV) (eV) (eV) (eV) (eV) ============================================================================== -1002000.00 0.00 7.916500+5 5.880400+2 0.0 0.0 228760.000 0.00 9.148000+3 1.504000+1 0.0 0.0 374820.000 0.00 1.823200+3 1.504000+1 0.0 0.0 500000.000 0.00 1.700300+5 1.504000+1 0.0 0.0 5000000.00 0.00 5.456100+4 1.504000+1 0.0 0.0 ------------------------------------------------------------------------------ -38128.0000 1.00 3.093200+2 4.779000+1 0.0 0.0 41260.0000 1.00 1.220000+3 3.331200+0 0.0 0.0 101800.000 1.00 7.314700+1 3.400000-1 0.0 0.0 181520.000 1.00 5.828200+1 1.140000+1 0.0 0.0 256860.000 1.00 1.544500+3 2.100000+1 0.0 0.0 316980.000 1.00 7.883000+2 1.040000+1 0.0 0.0 330130.000 1.00 2.789100+3 1.504000+1 0.0 0.0 445350.000 1.00 1.793900+4 1.504000+1 0.0 0.0 462890.000 1.00 7.698600+3 1.504000+1 0.0 0.0 500000.000 1.00 1.825900+1 1.504000+1 0.0 0.0 5000000.00 1.00 6.249800+3 1.504000+1 0.0 0.0 ============================================================================== Atomic Weight Ratio of Isotope------- 2.052000+2 L Dependent Scattering Radius-------- 0.0 Angular Momentum (L)----------------- 1 Number of Resonances----------------- 102 WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING L Dependent Scattering Radius in the Evaluation is Zero. Have Defined it to be Equal to the Scattering Radius. (see, ENDF/B-VI Formats and Procedures Manual, page 2.11) ------------------------------------------------------------------------------ WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING L= 1 J = 1.000 Corresponds to 2 Resonance Sequences. ------------------------------------------------------------------------------ ============================================================================== Reich-Moore Resonance Parameters ============================================================================== Energy J Value Neutron Capture Fission-1 Fission-2 (eV) (eV) (eV) (eV) (eV) ============================================================================== 82091.0000 0.00 1.006200+2 4.698800-1 0.0 0.0 103570.000 0.00 2.551400+2 4.698800-1 0.0 0.0 135260.000 0.00 1.342300+2 4.698800-1 0.0 0.0 179230.000 0.00 8.738000+1 4.698800-1 0.0 0.0 182100.000 0.00 4.195400+1 4.698800-1 0.0 0.0 186320.000 0.00 1.694400+2 4.698800-1 0.0 0.0 197010.000 0.00 2.807300+1 4.698800-1 0.0 0.0 199520.000 0.00 6.152300+1 4.698800-1 0.0 0.0 200990.000 0.00 2.476500+1 4.698800-1 0.0 0.0 207620.000 0.00 1.964300+2 4.698800-1 0.0 0.0 269450.000 0.00 4.491700+1 4.300000-1 0.0 0.0 276440.000 0.00 9.079400+1 4.698800-1 0.0 0.0 290190.000 0.00 1.626700+2 4.698800-1 0.0 0.0 296470.000 0.00 3.664900+1 4.698800-1 0.0 0.0 301390.000 0.00 9.721600+1 4.698800-1 0.0 0.0 317400.000 0.00 6.631800+2 4.698800-1 0.0 0.0 372860.000 0.00 2.581900+1 4.698800-1 0.0 0.0 376970.000 0.00 2.804500+1 4.698800-1 0.0 0.0 378600.000 0.00 1.182300+2 4.698800-1 0.0 0.0 383580.000 0.00 6.266700+1 4.698800-1 0.0 0.0 396150.000 0.00 2.663500+2 4.698800-1 0.0 0.0 405700.000 0.00 1.012500+3 4.698800-1 0.0 0.0 436300.000 0.00 6.851700+2 4.698800-1 0.0 0.0 5000000.00 0.00 2.090800+7 4.698800-1 0.0 0.0 ------------------------------------------------------------------------------ 12357.0000 1.00 1.133300+0 4.698800-1 0.0 0.0 16758.0000 1.00 3.700000+1 6.800000-2 0.0 0.0 37720.0000 1.00 5.000000+1 8.000000-1 0.0 0.0 73021.0000 1.00 3.204200+1 1.900000-2 0.0 0.0 90173.0000 1.00 2.712600+2 1.980000+0 0.0 0.0 115170.000 1.00 9.399401+2 1.760000+0 0.0 0.0 127900.000 1.00 6.912101+2 2.850000+0 0.0 0.0 130210.000 1.00 9.949300+1 9.800000-1 0.0 0.0 132160.000 1.00 6.343200+1 3.900000-2 0.0 0.0 145410.000 1.00 1.184300+2 4.698800-1 0.0 0.0 148220.000 1.00 2.518000+1 4.698800-1 0.0 0.0 149140.000 1.00 1.005500+1 4.698800-1 0.0 0.0 155730.000 1.00 1.127200+2 6.900000-1 0.0 0.0 168500.000 1.00 1.904700+2 1.160000-1 0.0 0.0 179010.000 1.00 1.252000+2 8.500000-1 0.0 0.0 180980.000 1.00 5.667800+1 1.200000+0 0.0 0.0 218450.000 1.00 1.213800+2 7.700000-2 0.0 0.0 229770.000 1.00 6.206600+2 4.698800-1 0.0 0.0 233260.000 1.00 5.408200+1 4.698800-1 0.0 0.0 243510.000 1.00 8.873400+1 4.600000-1 0.0 0.0 249880.000 1.00 1.648500+2 1.740000-1 0.0 0.0 262170.000 1.00 9.899900+1 4.698800-1 0.0 0.0 265430.000 1.00 2.081700+2 4.698800-1 0.0 0.0 284680.000 1.00 9.784000+1 1.450000-1 0.0 0.0 287440.000 1.00 4.173100+1 4.698800-1 0.0 0.0 297890.000 1.00 2.648800+2 7.400000-1 0.0 0.0 299870.000 1.00 3.331800+1 4.698800-1 0.0 0.0 306110.000 1.00 3.676000+1 4.698800-1 0.0 0.0 314080.000 1.00 2.005200+2 4.698800-1 0.0 0.0 335610.000 1.00 2.761800+2 1.430000+0 0.0 0.0 368770.000 1.00 5.231400+1 4.300000-1 0.0 0.0 370080.000 1.00 1.853900+2 4.698800-1 0.0 0.0 379290.000 1.00 4.844300+1 4.698800-1 0.0 0.0 382520.000 1.00 6.677600+1 4.698800-1 0.0 0.0 385910.000 1.00 5.191300+1 4.698800-1 0.0 0.0 424270.000 1.00 2.175500+2 4.698800-1 0.0 0.0 427100.000 1.00 1.458400+2 4.698800-1 0.0 0.0 452500.000 1.00 4.901100+1 1.422200+0 0.0 0.0 466300.000 1.00 2.806800+2 4.698800-1 0.0 0.0 5000000.00 1.00 1.787300+7 4.698800-1 0.0 0.0 ------------------------------------------------------------------------------ 3063.00000 2.00 1.200000-1 1.400000-1 0.0 0.0 10185.0000 2.00 5.600000-1 1.230000-1 0.0 0.0 29390.0000 2.00 1.600000+1 1.750000-1 0.0 0.0 68360.0000 2.00 5.600000+0 1.000000-1 0.0 0.0 82980.0000 2.00 2.562500+1 1.800000-1 0.0 0.0 87740.0000 2.00 7.469200+0 6.300000-2 0.0 0.0 98391.0000 2.00 1.000300+2 4.400000-2 0.0 0.0 112040.000 2.00 4.623900+1 2.100000-1 0.0 0.0 127670.000 2.00 1.255400+2 4.698800-1 0.0 0.0 136490.000 2.00 2.099700+1 1.800000-1 0.0 0.0 139690.000 2.00 1.675600+2 1.090000-1 0.0 0.0 153770.000 2.00 1.025800+1 1.130000-1 0.0 0.0 156720.000 2.00 5.002200+0 4.698800-1 0.0 0.0 158920.000 2.00 4.140200+1 9.800000-1 0.0 0.0 171130.000 2.00 1.712600+2 5.300000-2 0.0 0.0 181180.000 2.00 9.326000+1 4.698800-1 0.0 0.0 210550.000 2.00 7.656500+1 6.800000-2 0.0 0.0 220230.000 2.00 1.624300+2 4.698800-1 0.0 0.0 224000.000 2.00 8.483100+1 7.900000-2 0.0 0.0 240670.000 2.00 3.990300+1 8.000000-2 0.0 0.0 249490.000 2.00 2.879200+2 2.440000-1 0.0 0.0 260530.000 2.00 8.279600+0 1.422200+0 0.0 0.0 285020.000 2.00 1.165100+2 4.698800-1 0.0 0.0 298130.000 2.00 3.607000+1 4.698800-1 0.0 0.0 323320.000 2.00 8.688800+1 4.698800-1 0.0 0.0 332410.000 2.00 8.580400+1 2.100000-1 0.0 0.0 336550.000 2.00 1.421200+2 4.698800-1 0.0 0.0 346480.000 2.00 7.677000+1 4.698800-1 0.0 0.0 349760.000 2.00 3.485800+1 4.698800-1 0.0 0.0 359780.000 2.00 1.232000+2 4.698800-1 0.0 0.0 395600.000 2.00 1.814000+2 2.860000-1 0.0 0.0 401500.000 2.00 2.557500+2 3.100000-1 0.0 0.0 402420.000 2.00 2.615800+2 4.698800-1 0.0 0.0 411950.000 2.00 7.338700+1 2.800000-1 0.0 0.0 420600.000 2.00 1.148800+2 4.698800-1 0.0 0.0 430210.000 2.00 1.298000+2 4.698800-1 0.0 0.0 446300.000 2.00 1.504600+2 4.698800-1 0.0 0.0 5000000.00 2.00 1.714200+7 2.800000-1 0.0 0.0 ------------------------------------------------------------------------------ WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING FOR L = 1 Expect Sum of Statistical Weights (GJ) to Equal (2*L + 1) = 3.000 Found = 2.250 Corrective Action Will be Taken to Correctly Calculate the Potential Scattering Cross Section - This Procedure is Based on the Decision of the National Nuclear Data Center, Brookhaven National Laboratory, Private Communication, Charles Dunford, (April 1991) ============================================================================== Atomic Weight Ratio of Isotope------- 2.052000+2 L Dependent Scattering Radius-------- 0.0 Angular Momentum (L)----------------- 2 Number of Resonances----------------- 21 WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING L Dependent Scattering Radius in the Evaluation is Zero. Have Defined it to be Equal to the Scattering Radius. (see, ENDF/B-VI Formats and Procedures Manual, page 2.11) ------------------------------------------------------------------------------ WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING L= 2 J = 2.000 Corresponds to 2 Resonance Sequences. ------------------------------------------------------------------------------ ============================================================================== Reich-Moore Resonance Parameters ============================================================================== Energy J Value Neutron Capture Fission-1 Fission-2 (eV) (eV) (eV) (eV) (eV) ============================================================================== 181490.000 1.00 4.673700+1 1.422200+0 0.0 0.0 256430.000 1.00 1.300800+3 1.422200+0 0.0 0.0 310210.000 1.00 6.355200+1 1.422200+0 0.0 0.0 316970.000 1.00 2.457800+1 1.422200+0 0.0 0.0 331230.000 1.00 2.666200+0 1.422200+0 0.0 0.0 5000000.00 1.00 2.477100+7 1.422200+0 0.0 0.0 ------------------------------------------------------------------------------ 209450.000 2.00 4.686900+2 1.422200+0 0.0 0.0 211770.000 2.00 5.397300+1 1.422200+0 0.0 0.0 309970.000 2.00 7.644500+1 1.422200+0 0.0 0.0 319560.000 2.00 2.488300+3 1.422200+0 0.0 0.0 355360.000 2.00 1.106900+2 1.422200+0 0.0 0.0 428400.000 2.00 3.443300+2 1.422200+0 0.0 0.0 457500.000 2.00 3.159200+0 1.422200+0 0.0 0.0 471500.000 2.00 1.168300+2 1.422200+0 0.0 0.0 5000000.00 2.00 9.376200+6 1.422200+0 0.0 0.0 ------------------------------------------------------------------------------ 254440.000 3.00 1.173500+2 1.422200+0 0.0 0.0 329740.000 3.00 3.072100+2 1.422200+0 0.0 0.0 414810.000 3.00 7.167400+2 1.422200+0 0.0 0.0 462700.000 3.00 1.679400+2 1.422200+0 0.0 0.0 472500.000 3.00 2.077300+3 1.422200+0 0.0 0.0 5000000.00 3.00 2.291900+6 1.422200+0 0.0 0.0 ------------------------------------------------------------------------------ WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING...WARNING FOR L = 2 Expect Sum of Statistical Weights (GJ) to Equal (2*L + 1) = 5.000 Found = 3.750 Corrective Action Will be Taken to Correctly Calculate the Potential Scattering Cross Section - This Procedure is Based on the Decision of the National Nuclear Data Center, Brookhaven National Laboratory, Private Communication, Charles Dunford, (April 1991) ============================================================================== Reconstructing Cross Sections from Resonance Parameters ============================================================================== E-Low E-High Points Type of Resonance Region (eV) (eV) Generated Messages ============================================================================== 1.000000-5 475000.000 12202 Resolved ============================================================================== Entire Resonance Region 12202 Points ============================================================================== Combining File 2 and File 3 Data ============================================================================== Reaction File 2 File 3 Combined Points Points Points Comments ============================================================================== Total 12202 870 13068 Elastic 12202 911 13109 Capture 12202 23 12221 ============================================================================== ============================================================================== Total Execution Time 0.93 Seconds ============================================================================== ****************************************************************************** End of ENDF/B Input Data ****************************************************************************** Core Allocation and Requirements ============================================================================== Sections Nodes Parameter Storage ============================================================================== Allocated 200 120000 120000 Required 5 130 141 ============================================================================== End of Run ============================================================================== ============================================================================== Total Execution Time 0.93 Seconds ==============================================================================