46-Pd-108

 46-Pd-108 JAEA       EVAL-Dec09 N.Iwamoto,K.Shibata              
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 4643                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-12 The resolved resonance parameters were evaluated by         
      K.Shibata.                                                  
      The data above the resolved resonance region were evaluated 
      and compiled by N.Iwamoto.                                  
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2  Resonance parameters                                       
  MT=151 Resolved and unresolved resonance parameters             
    Resolved resonance region (MLBW formula) : below 9 keV        
      In JENDL-3.3, the parameters were mainly taken from the     
      recommendation of Mughabghab et al./1/  The average         
      radiation with of 77 meV/1/ was assumed.                    
      In JENDL-4, the data for 33 eV - 2.3 keV were replaced      
      with the ones obtained by Smith et al./2/  A value of       
      77 meV was used for unknown radiation widths.  Spin of the  
      p-wave resonance was determined from the spin distribution  
      of level density randomly.  The parameters for 32.98 and    
      90.98-eV s-wave resonances were alightly adjusted.          
                                                                  
    Unresolved resonance region : 9 keV - 160 keV                 
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /3/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      OPTMAN /4/ and CCONE /5/. The unresolved parameters         
      should be used only for self-shielding calculation.         
                                                                  
      Thermal cross sections and resonance integrals at 300 K     
      ----------------------------------------------------------  
                       0.0253 eV           res. integ. (*)        
                        (barn)               (barn)               
      ----------------------------------------------------------  
       Total           1.0007e+01                                 
       Elastic         1.9618e+00                                 
       n,gamma         8.0455e+00           2.4317e+02            
       n,alpha         4.3578e-22                                 
      ----------------------------------------------------------  
         (*) Integrated from 0.5 eV to 10 MeV.                    
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    Sum of partial cross sections.                                
                                                                  
  MT=  2 Elastic scattering cross section                         
    Obtained by subtracting non-elastic scattering cross sections 
      from total cross section.                                   
                                                                  
  MT=  4 (n,n') cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /5/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /5/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /5/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /5/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /5/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /5/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /5/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /5/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /5/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /5/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /5/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /5/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,1,3,10,14 (see Table 1)                   
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./6/ (+)                      
      proton   omp: Koning,A.J. and Delaroche,J.P./7/             
      deuteron omp: Lohr,J.M. and Haeberli,W./8/                  
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./9/      
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./9/      
      alpha    omp: Huizenga,J.R. and Igo,G./10/                  
      (+) omp parameters were modified.                           
                                                                  
  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                            
    * Width fluctuation correction/14/ was applied.               
    * Neutron, proton, deuteron, triton, He3, alpha and gamma     
      decay channel were taken into account.                      
    * Transmission coefficients of neutrons 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/15/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of generalized Lorentzian form  
      /16/,/17/ was used for E1 transition.                       
      For M1 and E2 transitions the standard Lorentzian form was  
      adopted. The prameters are shown in Table 3.                
                                                                  
                                                                  
------------------------------------------------------------------
                              Tables                              
------------------------------------------------------------------
                                                                  
Table 1. Level Scheme of Pd-108                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +  *                                           
   1  0.43394   2  +  *                                           
   2  0.93114   2  +                                              
   3  1.04825   4  +  *                                           
   4  1.05278   0  +                                              
   5  1.31422   0  +                                              
   6  1.33522   3  +                                              
   7  1.44118   2  +                                              
   8  1.53996   1  +                                              
   9  1.62520   4  +                                              
  10  1.77116   6  +  *                                           
  11  1.95700   4  +                                              
  12  1.98986   4  +                                              
  13  2.01500   1  -                                              
  14  2.04665   3  -  *                                           
  15  2.09867   2  +                                              
  16  2.14100   0  +                                              
  17  2.21801   2  +                                              
  18  2.28121   1  -                                              
  19  2.28249   0  +                                              
  20  2.32480   5  -                                              
  21  2.36200   2  +                                              
  22  2.39140   2  +                                              
  23  2.39750   8  +                                              
  24  2.40410   0  +                                              
  25  2.41800   0  +                                              
  26  2.42200   6  +                                              
  27  2.46600   4  +                                              
  28  2.47757   2  +                                              
  29  2.53100   0  +                                              
  30  2.53640   0  +                                              
  31  2.54020   4  +                                              
  32  2.54840   8  +                                              
  33  2.57800   0  +                                              
  -------------------                                             
  *) Coupled levels in CC calculation                             
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Pd-109 16.0000  1.1494  3.8267  0.6463 -1.8210  6.7457         
   Pd-108 14.3000  2.3094  3.1785  0.6359  0.3436  6.8413         
   Pd-107 15.0000  1.1601  3.1932  0.6723 -1.5375  6.6188         
   Pd-106 14.4000  2.3311  2.3412  0.6736  0.1590  7.3089         
   Rh-108 15.6000  0.0000  4.1884  0.5114 -1.3068  3.3132         
   Rh-107 13.0075  1.1601  4.0295  0.7116 -1.4170  6.5036         
   Rh-106 14.2000  0.0000  3.7991  0.5945 -1.6674  4.0000         
   Rh-105 15.8000  1.1711  3.4219  0.6193 -1.2405  6.1130         
   Ru-107 15.5000  1.1601  4.4476  0.6172 -1.4266  6.1858         
   Ru-106 13.4840  2.3311  4.1609  0.6686  0.0022  7.2594         
   Ru-105 15.3000  1.1711  4.2450  0.6623 -1.8991  6.8479         
   Ru-104 13.2688  2.3534  3.6273  0.6755  0.1955  7.1592         
   Ru-103 14.0500  1.1824  3.5429  0.7267 -1.9541  7.2112         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Pd-109                   
  --------------------------------------------------------        
  * E1: ER = 15.92 (MeV) EG = 7.18 (MeV) SIG = 199.00 (mb)        
  * M1: ER =  8.58 (MeV) EG = 4.00 (MeV) SIG =   1.14 (mb)        
  * E2: ER = 13.19 (MeV) EG = 4.80 (MeV) SIG =   2.41 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
 2) Smith, D.A. et al.: Phys. Rev., C65, 024607 (2002).           
 3) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 4) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).   
 5) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 6) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 7) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
 8) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
 9) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
10) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
11) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
12) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
13) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
14) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
15) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
16) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
17) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).