46-Pd-105

 46-Pd-105 JAEA       EVAL-Dec09 N.Iwamoto,K.Shibata              
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 4634                               
-----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 2.0485 keV   
      The parameters were based on the basis of the data measured 
      by Staveloz et al./1/.  Data of Bollinger et al./2/ and     
      of Coceva et al./3/ were also taken into account to         
      determine the angular momentum l and the spin j.  The       
      average radiation width of 0.15 ev was assumed for s-wave   
      levels.  Two negative resonances were added so as to        
      reproduce the thermal capture and scattering cross sections 
      given by Mughabghab et al./4/  Total spin j of some         
      resonances was tentatively estimated with a random number   
      method.  Neutron orbital angular momentum l of some         
      resonances was estimated with a method of Bollinger and     
      Thomas/5/.                                                  
      In JENDL-4, the data for 3.9 - 804 eV were replaced with    
      the ones obtained by Smith et al./6/  The values of         
      unknown J were determined from the spin distribution of     
      level density randomly.                                     
                                                                  
    Unresolved resonance region : 2.0485 keV - 100 keV            
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /7/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      OPTMAN /8/ and CCONE /9/. 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           2.5547e+01                                 
       Elastic         5.1104e+00                                 
       n,gamma         2.0436e+01           1.0256e+02            
       n,alpha         2.2939e-04                                 
      ----------------------------------------------------------  
         (*) 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 /9/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 24 (n,2na) cross section                                    
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 41 (n,2np) cross section                                    
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /9/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /9/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /9/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /9/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /9/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /9/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /9/.                               
                                                                  
  MT=111 (n,2p) cross section                                     
    Calculated with CCONE code /9/.                               
                                                                  
  MT=112 (n,pa) cross section                                     
    Calculated with CCONE code /9/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /9/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 24 (n,2na) reaction                                         
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 41 (n,2np) reaction                                         
    Calculated with CCONE code /9/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /9/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /9/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /9/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,2,15,27 (see Table 1)                     
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./10/ (+)                     
      proton   omp: Koning,A.J. and Delaroche,J.P./11/            
      deuteron omp: Lohr,J.M. and Haeberli,W./12/                 
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./13/     
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./13/     
      alpha    omp: Huizenga,J.R. and Igo,G./14/                  
      (+) omp parameters were modified.                           
                                                                  
  2) Two-component exciton model/15/                              
    * Global parametrization of Koning-Duijvestijn/16/            
      was used.                                                   
    * Gamma emission channel/17/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/18/ 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/19/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of generalized Lorentzian form  
      /20/,/21/ 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-105                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000  5/2 +  *                                           
   1  0.28051  3/2 +                                              
   2  0.30625  7/2 +  *                                           
   3  0.31922  5/2 +                                              
   4  0.34451  1/2 +                                              
   5  0.44238  7/2 +                                              
   6  0.44700  5/2 +                                              
   7  0.48914 11/2 -                                              
   8  0.53500  3/2 +                                              
   9  0.56075  3/2 +                                              
  10  0.64453  7/2 -                                              
  11  0.65070  3/2 +                                              
  12  0.67317  1/2 +                                              
  13  0.69666  7/2 +                                              
  14  0.72722  5/2 +                                              
  15  0.78194  9/2 +  *                                           
  16  0.78700  1/2 +                                              
  17  0.80800  7/2 -                                              
  18  0.90198  5/2 +                                              
  19  0.92100  5/2 +                                              
  20  0.92913  5/2 +                                              
  21  0.93900  1/2 +                                              
  22  0.96140  3/2 -                                              
  23  0.96238  3/2 +                                              
  24  0.97015 15/2 -                                              
  25  0.97200  3/2 -                                              
  26  1.01155  7/2 -                                              
  27  1.01171 11/2 +  *                                           
  28  1.07220  5/2 -                                              
  29  1.07440  5/2 +                                              
  30  1.07500  1/2 +                                              
  31  1.08796  3/2 -                                              
  32  1.09842  5/2 +                                              
  33  1.10210  3/2 +                                              
  34  1.12533  3/2 +                                              
  35  1.14081  1/2 +                                              
  36  1.14235  3/2 -                                              
  37  1.17770  5/2 +                                              
  -------------------                                             
  *) 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-106 14.4000  2.3311  2.3412  0.6736  0.1590  7.3089         
   Pd-105 14.9000  1.1711  2.0672  0.7067 -1.5220  6.8969         
   Pd-104 13.5000  2.3534  1.1560  0.7879 -0.3130  8.4969         
   Pd-103 13.8438  1.1824  0.6498  0.8078 -1.6903  7.7695         
   Rh-105 15.8000  1.1711  3.4219  0.6193 -1.2405  6.1130         
   Rh-104 14.1000  0.0000  2.9724  0.6799 -2.3482  5.1092         
   Rh-103 15.8000  1.1824  2.3988  0.6206 -0.9205  5.8890         
   Rh-102 15.0000  0.0000  1.6557  0.6874 -2.3483  5.3149         
   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         
   Ru-102 14.0000  2.3764  2.6482  0.6699  0.2865  7.1898         
   Ru-101 13.6288  1.1940  2.2461  0.7582 -1.6413  7.1993         
   Ru-100 13.8300  2.4000  1.2905  0.7521 -0.0727  8.1397         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Pd-106                   
  --------------------------------------------------------        
  * E1: ER = 15.92 (MeV) EG = 7.18 (MeV) SIG = 199.00 (mb)        
  * M1: ER =  8.66 (MeV) EG = 4.00 (MeV) SIG =   1.23 (mb)        
  * E2: ER = 13.31 (MeV) EG = 4.84 (MeV) SIG =   2.46 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Staveloz, P., et al.: "Proc. Specialist's Meeting on Neutron  
    Cross Sections of Fission Product Nuclei, Bologna 1979",      
    NEANDC(E)209L, 53 (1979).                                     
 2) Bollinger, L.M., et al.: "Proc. Congres International de      
    Physique Nucleaire, Paris 1964", Vol.2, 673 (1964).           
 3) Coceva, C., et al.: Phys. Lett., 16, 159 (1965).              
 4) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I,     
    Part A", Academic Press (1981).                               
 5) Bollinger, L.M., Thomas, G.E.: Phys. Rev., 171,1293(1968).    
 6) Smith, D.A. et al.: Phys. Rev., C65, 024607 (2002).           
 7) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 8) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).   
 9) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
10) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
11) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
12) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
13) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
14) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
15) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
16) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
17) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
18) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
19) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
20) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
21) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).