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
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 ENDF/B Input and Output Data Filenames
 ENDF.IN                                                     
 RECENT.OUT                                                  
 ==============================================================================
 Requested MAT Ranges
 ==============================================================================
    Mimimum    Maximum
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          1       9999
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 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       
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  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
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 ******************************************************************************
 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
 ==============================================================================
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 Total Execution Time                0.93 Seconds
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