82-Pb-204

 82-Pb-204 JAEA       EVAL-MAR10 O.Iwamoto, N.Iwamoto             
                      DIST-SEP14                       20150816   
----JENDL-4.0u1       MATERIAL 8225                               
-----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 75 keV                         
    Parameters were evaluated from the data of Mughabghab /1/     
    and Domingo-Pardo et al. /2/.                                 
    Effective scattering radius of 9.5 fm was selected.           
                                                                  
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total          1.29371E+01                                   
     Elastic        1.22339E+01                                   
     n,gamma        7.03163E-01          2.38541E+00              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    Based on experimental data/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 75 keV was calculated from      
    resonance parameters, by assuming a mean alpha width of       
    7.0e-8 eV for s-wave resonances and 1.3e-7 eV for p- and      
    d-wave resonances.                                            
    The cross section was averaged in suitable energy intervals.  
    Above 75 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 /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/5/. Evaluated data with the other methods are       
  described bellow.                                               
                                                                  
  MT=1 Total cross section                                        
  1.0e-5 eV to 75 keV(RRR): given by a sum of the covariance data 
  of the elastic scattering and the neutron capture cross         
  sections.                                                       
  75 keV to 2 MeV: obtained based on the average cross section    
  of the experimental data/3/.                                    
  2 MeV to 20 MeV: obtained by the CCONE-KALMAN.                  
                                                                  
  MT=2 Elastic scattering cross sections                          
  1.0e-5 eV to 75 keV(RRR): obtained by the kernel                
  approximation/6/.                                               
  75 keV to 20 MeV: obtained by the CCONE-KALMAN.                 
                                                                  
  MT=102 Capture cross section                                    
  1.0e-5 eV to 75 keV(RRR): obtained by the kernel                
  approximation/6/.                                               
  75 keV 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./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-204                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +                                              
   1  0.89917   2  +                                              
   2  1.27400   4  +                                              
   3  1.35117   2  +                                              
   4  1.56327   4  +                                              
   5  1.58250   0  +                                              
   6  1.58276   2  +                                              
   7  1.60476   3  +                                              
   8  1.66528   2  +                                              
   9  1.68120   1  +                                              
  10  1.71220   3  +                                              
  11  1.72997   0  +                                              
  12  1.76108   2  +                                              
  13  1.81745   4  +                                              
  14  1.87211   1  +                                              
  15  1.93329   1  +                                              
  -------------------                                             
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   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         
   Pb-203 25.9774  0.8422 -5.8686  0.5356  0.2693  4.6262         
   Pb-202 23.5189  1.6886 -5.1155  0.6087  0.5389  6.7723         
   Tl-204 23.7127  0.0000 -7.3974  0.7420 -1.6150  8.6194         
   Tl-203 23.6158  0.8422 -6.3748  0.6939 -0.7207  7.9782         
   Tl-202 23.5189  0.0000 -5.8533  0.5817 -0.5512  4.0888         
   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         
   Hg-199 23.2277  0.8507 -4.0893  0.6457 -1.1776  7.2191         
   Hg-198 23.1305  1.7056 -3.4174  0.5931  0.0911  6.9096         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Pb-205                   
  --------------------------------------------------------        
  * E1: ER = 13.77 (MeV) EG = 3.89 (MeV) SIG = 579.28 (mb)        
  * M1: ER =  6.95 (MeV) EG = 4.00 (MeV) SIG =   0.89 (mb)        
  * E2: ER = 10.68 (MeV) EG = 3.65 (MeV) SIG =   5.35 (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. C75, 015806 (2007).       
 3) R.F.Carlton et al.: Phys Rev. C67, 024601 (2003).             
 4) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007).            
 5) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in         
    Japanese.                                                     
 6) P.Pblozinsky et al.: NL-91287-2010 (2010).                    
 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).