82-Pb-208

 82-Pb-208 JAEA       EVAL-MAR10 O.Iwamoto, N.Iwamoto             
                      DIST-SEP14                       20150816   
----JENDL-4.0u1       MATERIAL 8237                               
-----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.                                                 
13-02 JENDL-4.0u1                                                 
      Covariance data (MF33/1,2,4,16,17,51-91,102,MF34/2) were    
      added.                                                      
                                                                  
                                                                  
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 1 MeV                          
    Parameters were evaluated from the data of Mughabghab /1/.    
    Effective scattering radius of 9.75 fm was selected.          
                                                                  
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total          1.14581E+01                                   
     Elastic        1.14579E+01                                   
     n,gamma        2.30374E-04          4.01052E-03              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    Based on experimental data/2,3/ 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 /4/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /4/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    The (n,a) cross section below 1 MeV was calculated from       
    resonance parameters, by assuming a mean alpha width of       
    1.0e-6 eV, except for negative resonance with 1.23e-2 eV, so  
    as to reproduce the cross section ratio at thermal energy /5/.
    The cross section was averaged in suitable energy intervals.  
    Above 1 MeV, 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 /4/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with CCONE code/4/.                
                                                                  
  MT= 17 (n,3n) reaction                                          
    Neutron spectra calculated with CCONE code/4/.                
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with CCONE code/4/.                
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with CCONE code/4/.                
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Neutron angular distributions and spectra calculated with     
    CCONE code/4/.                                                
                                                                  
  MT= 102 Capture cross section                                   
    Gamma-ray spectra calculated with CCONE code/4/.              
                                                                  
MF=33 Covariances of neutron cross sections                       
  Covariance data were basically evaluated with CCONE code/4/ and 
  KALMAN code/6/. Evaluated data with the other methods are       
  described bellow.                                               
                                                                  
  MT=1 Total cross section                                        
  1.0e-5 eV to 1 MeV(RRR): given by a sum of the covariance data  
  of the elastic scattering and the neutron capture cross         
  sections.                                                       
  1 MeV to 7 MeV: obtained based on the average cross section     
  of the experimental data/2/,/3/.                                
  6 MeV to 20 MeV: obtained by the CCONE-KALMAN.                  
                                                                  
  MT=2 Elastic scattering cross sections                          
  1.0e-5 eV to 1 MeV(RRR): obtained by the kernel                 
  approximation/7/.                                               
  1 MeV to 20 MeV: obtained by the CCONE-KALMAN.                  
                                                                  
  MT=102 Capture cross section                                    
  1.0e-5 eV to 1 MeV(RRR): obtained by the kernel                 
  approximation/7/.                                               
  1 MeV to 20 MeV: obtained by the CCONE-KALMAN.                  
                                                                  
MF=34 Covariances for Angular Distributions                       
  MT=2 Elastic scattering                                         
  Obtained by the CCONE-KALMAN.                                   
                                                                  
***************************************************************** 
*      Nuclear Model Calculation with CCONE code /4/            * 
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
      neutron OMP: Koning et al./8/                               
      proton  OMP: Koning and Delaroche /9/                       
      alpha   OMP: Avrigeanu et al./10/ with modification         
                                                                  
  2) Two-component exciton model/11/                              
    * Global parametrization of Koning-Duijvestijn/12/            
      was used.                                                   
    * Gamma emission channel/13/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Moldauer width fluctuation correction/14/ 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/15/,/16/       
      was used. The prameters are shown in Table 3.               
                                                                  
                                                                  
------------------------------------------------------------------
                              Tables                              
------------------------------------------------------------------
                                                                  
Table 1. Level Scheme of Pb-208                                   
  ---------------------------------                               
  No.  Ex(MeV)  J  PI, DWBA: L beta                               
  ---------------------------------                               
   0  0.00000   0  +                                              
   1  2.61455   3  -         3 0.09                               
   2  3.19774   5  -         5 0.03                               
   3  3.47511   4  -                                              
   4  3.70844   5  -         5 0.02                               
   5  3.91980   6  -                                              
   6  3.94644   4  -                                              
   7  3.96096   5  -         5 0.01                               
   8  3.99570   5  -                                              
   9  4.03700   7  -         7 0.02                               
  10  4.04500   6  -                                              
  11  4.05050   3  -         3 0.02                               
  12  4.08540   2  +                                              
  13  4.10600   3  -         3 0.03                               
  14  4.12531   4  -                                              
  15  4.14100   2  +                                              
  16  4.15900   2  +                                              
  17  4.18041   5  -                                              
  18  4.20540   6  -                                              
  19  4.22950   2  -                                              
  20  4.23000   4  -                                              
  21  4.25350   3  -         3 0.07                               
  22  4.26240   5  -                                              
  23  4.29617   5  -                                              
  24  4.31800   2  +                                              
  25  4.32320   4  +                                              
  ---------------------------------                               
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Pb-209 24.1961  0.8301 -8.6072  0.6523  0.8730  5.6376         
   Pb-208 26.5095  1.6641 -9.9611  0.6945  1.6735  8.9801         
   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         
   Tl-208 24.0995  0.0000 -7.9260  0.7127 -0.9908  7.4338         
   Tl-207 24.0029  0.8341 -9.1989  0.6784  1.0665  6.0451         
   Tl-206 23.9062  0.0000 -9.0786  0.7703 -0.8614  9.5127         
   Hg-207 24.0029  0.8341 -6.5458  0.4118  1.3479  1.8341         
   Hg-206 23.9062  1.6722 -8.0262  0.6306  1.6426  6.0277         
   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         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Pb-209                   
  --------------------------------------------------------        
  * E1: ER = 12.00 (MeV) EG = 4.00 (MeV) SIG = 500.00 (mb)        
  * M1: ER =  6.91 (MeV) EG = 4.00 (MeV) SIG =   2.29 (mb)        
  * E2: ER = 10.62 (MeV) EG = 3.60 (MeV) SIG =   5.32 (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) R.F.Carlton et al.: Bull. Amer. Phys. Soc., 36, 1349(J10-10)  
     (1991)                                                       
 3) J.A.Harvey: private communication in EXFOR(13732002).         
 4) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007).            
 5) J.Alam and M.I.Sehgal: Nucl. Phys. A205, 614 (1973)           
 6) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in         
    Japanese.                                                     
 7) P.Pblozinsky et al.: NL-91287-2010 (2010).                    
 8) A.J.Koning et al.: Nucl. Sci. Eng., 156, 357 (2007).          
 9) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).      
10) V.Avrigeanu,P.E.Hodgson, and M.Avrigeanu, Report OUNP-94-02   
    (1994), Phys. Rev. C49,2136 (1994).                           
11) C.Kalbach: Phys. Rev. C33, 818 (1986).                        
12) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004).     
13) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985).     
14) P.A.Moldauer: Nucl. Phys. A344, 185 (1980).                   
15) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990).                
16) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990).