82-Pb-206

 82-Pb-206 JAEA       EVAL-MAR10 O.Iwamoto, N.Iwamoto             
                      DIST-MAY10                       20100311   
----JENDL-4.0         MATERIAL 8231                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
10-03 Resonace parameters were evaluated by N. Iwamoto.           
      Cross sections and spectra were evaluated and compiled by   
      O. Iwamoto.                                                 
                                                                  
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2 Resonance parameters                                        
  MT=151  Resolved resonance parameters for Reich-Moore formula.  
    Resonance ranges: 1.0e-5 eV to 820 keV                        
    Parameters were evaluated from the data of Mughabghab /1/,    
    Domingo-Pardo et al. /2/ and Borella et al. /3/.              
    Effective scattering radius of 9.7 fm was selected.           
                                                                  
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total          1.08757E+01                                   
     Elastic        1.08491E+01                                   
     n,gamma        2.65634E-02          1.14757E-01              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    Based on experimental data/4,5/ and CCONE calculation.        
                                                                  
  MT=  2 Elastic scattering cross section                         
    Obtained by subtracting non-elastic cross sections from total 
    cross sections.                                               
                                                                  
  MT=  4,51-91 (n,n') cross section                               
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /6/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    The (n,a) cross section below 820 keV was calculated from     
    resonance parameters, by assuming a mean alpha width of       
    9.0e-8 eV for s-wave resonances and 1.5e-7 eV for p- and      
    d-wave resonances.                                            
    The cross section was averaged in suitable energy intervals.  
    Above 820 keV, the cross section was connected smoothly to the
    CCONE calculation.                                            
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /6/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with CCONE code/6/.                
                                                                  
  MT= 17 (n,3n) reaction                                          
    Neutron spectra calculated with CCONE code/6/.                
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with CCONE code/6/.                
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with CCONE code/6/.                
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Neutron angular distributions and spectra calculated with     
    CCONE code/6/.                                                
                                                                  
  MT= 102 Capture cross section                                   
    Gamma-ray spectra calculated with CCONE code/6/.              
                                                                  
***************************************************************** 
*      Nuclear Model Calculation with CCONE code /6/            * 
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
      neutron OMP: Koning et al./7/                               
      proton  OMP: Koning and Delaroche /8/                       
      alpha   OMP: Avrigeanu et al./9/ with modification          
                                                                  
  2) Two-component exciton model/10/                              
    * Global parametrization of Koning-Duijvestijn/11/            
      was used.                                                   
    * Gamma emission channel/12/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Moldauer width fluctuation correction/13/ was included.     
    * Neutron, proton, alpha and gamma decay channels were        
      included.                                                   
    * Transmission coefficients of neutrons, proton and alpha     
      were taken from optical model calculation.                  
    * The level scheme of the target is shown in Table 1.         
    * Level density formula of constant temperature and Fermi-gas 
      model were used with shell energy correction and collective 
      enhancement factor. Parameters are shown in Table 2.        
    * Gamma-ray strength function of Kopecky et al/14/,/15/       
      was used. The prameters are shown in Table 3.               
                                                                  
                                                                  
------------------------------------------------------------------
                              Tables                              
------------------------------------------------------------------
                                                                  
Table 1. Level Scheme of Pb-206                                   
  ---------------------------------                               
  No.  Ex(MeV)  J  PI, DWBA: L beta                               
  ---------------------------------                               
   0  0.00000   0  +                                              
   1  0.80310   2  +         2 0.03                               
   2  1.16600   0  +                                              
   3  1.34054   3  +                                              
   4  1.46680   2  +         2 0.01                               
   5  1.68404   4  +         4 0.03                               
   6  1.70350   1  +                                              
   7  1.78420   2  +                                              
   8  1.99771   4  +         4 0.02                               
   9  2.14790   2  +         2 0.01                               
  10  2.19670   3  -                                              
  11  2.20021   7  -         7 0.02                               
  12  2.23570   4  +                                              
  13  2.31500   0  +                                              
  14  2.38419   6  -                                              
  15  2.39139   1  +                                              
  16  2.42310   2  +         2 0.01                               
  ---------------------------------                               
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Pb-207 25.6831  0.8341 -9.5535  0.7157  0.5055  8.8352         
   Pb-206 26.2968  1.6722 -8.3925  0.7059  0.4426 10.1593         
   Pb-205 26.1904  0.8381 -7.5629  0.6715 -0.4353  8.0994         
   Pb-204 26.0839  1.6803 -6.7012  0.6812 -0.2552  9.6416         
   Tl-206 23.9062  0.0000 -9.0786  0.7703 -0.8614  9.5127         
   Tl-205 23.8095  0.8381 -7.9177  0.7491 -0.5502  9.6384         
   Tl-204 23.7127  0.0000 -7.3974  0.7420 -1.6150  8.6194         
   Hg-205 23.8095  0.8381 -7.7955  0.6870  0.1648  7.1525         
   Hg-204 23.7127  1.6803 -7.2319  0.7544 -0.2408 10.8925         
   Hg-203 23.6158  0.8422 -6.5295  0.7165 -0.9421  8.7294         
   Hg-202 23.5189  1.6886 -5.9276  0.7363 -0.7512 10.4860         
   Hg-201 23.4219  0.8464 -5.2630  0.6922 -1.2829  8.2740         
   Hg-200 23.3248  1.6971 -4.7209  0.6692 -0.3684  8.5593         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Pb-207                   
  --------------------------------------------------------        
  * E1: ER = 13.74 (MeV) EG = 3.88 (MeV) SIG = 585.51 (mb)        
  * M1: ER =  6.93 (MeV) EG = 4.00 (MeV) SIG =   0.90 (mb)        
  * E2: ER = 10.65 (MeV) EG = 3.63 (MeV) SIG =   5.33 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) S.F.Mughabghab: "Atlas of Neutron Resonances, Fifth           
     Edition: Resonance Parameters and Thermal Cross Sections.    
     Z=1-100", Elsevier Science (2006).                           
 2) C.Domingo-Pardo et al.:  Phys. Rev., C76, 045805 (2007).      
 3) A.Borella et al.: Phys. Rev., C76, 014605 (2007).             
 4) D.J.Horen et al.: Phys Rev. C20, 478 (1979).                  
 5) D.G.Foster Jr, D.W.Glasgow: Phys. Rev. C3, 576 (1971).        
 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007).            
 7) A.J.Koning et al.: Nucl. Sci. Eng., 156, 357 (2007).          
 8) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).      
 9) V.Avrigeanu,P.E.Hodgson, and M.Avrigeanu, Report OUNP-94-02   
    (1994), Phys. Rev. C49,2136 (1994).                           
10) C.Kalbach: Phys. Rev. C33, 818 (1986).                        
11) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004).     
12) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985).     
13) P.A.Moldauer: Nucl. Phys. A344, 185 (1980).                   
14) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990).                
15) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990).