30-Zn- 65

 30-Zn- 65 JAEA       EVAL-Dec09 N.Iwamoto                        
                      DIST-MAY10                       20100327   
----JENDL-4.0         MATERIAL 3028                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-12 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             
    No resolved resonance parameters                              
                                                                  
    Unresolved resonance region : 140 eV - 110 keV                
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /1/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      OPTMAN /2/ and CCONE /3/. 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           7.2310e+01                                 
       Elastic         6.1686e+00                                 
       n,gamma         6.4023e+01           3.9187e+01            
       n,p             3.0592e-03                                 
       n,alpha         2.0007e+00                                 
      ----------------------------------------------------------  
         (*) 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 /3/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 24 (n,2na) cross section                                    
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 41 (n,2np) cross section                                    
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /3/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /3/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /3/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /3/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /3/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /3/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /3/.                               
    The cross section at thermal energy was evaluated so as to    
      reproduce the value recommended by Mughabghab/4/.           
                                                                  
  MT=108 (n,2a) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT=111 (n,2p) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT=112 (n,pa) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT=115 (n,pd) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT=116 (n,pt) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /3/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 24 (n,2na) reaction                                         
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 41 (n,2np) reaction                                         
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /3/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /3/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /3/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,5 (see Table 1)                           
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./5/ (+)                      
      proton   omp: Koning,A.J. and Delaroche,J.P./6/             
      deuteron omp: Lohr,J.M. and Haeberli,W./7/                  
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./8/      
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./8/      
      alpha    omp: Huizenga,J.R. and Igo,G./9/                   
      (+) omp parameters were modified.                           
                                                                  
  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                            
    * Width fluctuation correction/13/ 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/14/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of standard Lorentzian form     
      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 Zn-65                                    
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000  5/2 -  *                                           
   1  0.05393  1/2 -                                              
   2  0.11513  3/2 -                                              
   3  0.20694  3/2 -                                              
   4  0.76870  5/2 -                                              
   5  0.86421  7/2 -  *                                           
   6  0.86692  1/2 -                                              
   7  0.90965  3/2 -                                              
   8  1.04739  5/2 -                                              
   9  1.06210  5/2 +                                              
  10  1.06551  9/2 +                                              
  11  1.25266  7/2 -                                              
  12  1.26342  9/2 -                                              
  13  1.34385  5/2 -                                              
  14  1.36908  5/2 +                                              
  15  1.46973  3/2 -                                              
  16  1.57705  3/2 -                                              
  17  1.58808  7/2 -                                              
  18  1.60300  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         
  --------------------------------------------------------        
   Zn- 66  9.4000  2.9542  0.7967  1.1121 -0.5948 11.1189         
   Zn- 65 10.1000  1.4884  0.5412  1.0267 -1.5890  8.8932         
   Zn- 64  9.4000  3.0000 -0.5895  1.3122 -2.1371 14.8774         
   Cu- 65  8.5438  1.4884  0.5181  1.1578 -1.5153  9.2308         
   Cu- 64  9.0000  0.0000 -0.2574  1.1602 -3.0278  8.1946         
   Cu- 63  9.6000  1.5119 -0.7921  1.1891 -2.1218 11.0245         
   Cu- 62  8.5999  0.0000 -1.6978  1.3701 -3.8967 11.5298         
   Ni- 64  9.2000  3.0000  0.5302  1.0082  0.8446  9.1343         
   Ni- 63  9.7000  1.5119  0.1580  1.0041 -0.8012  7.9800         
   Ni- 62  8.7000  3.0480 -0.7667  1.2725 -0.5439 12.7980         
   Ni- 61  9.6000  1.5364 -1.2520  1.1257 -1.0688  9.6338         
   Ni- 60  8.5000  3.0984 -2.2445  1.4738 -1.5214 16.9599         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Zn- 66                   
  --------------------------------------------------------        
  * E1: ER = 16.23 (MeV) EG = 3.27 (MeV) SIG =  41.40 (mb)        
        ER = 19.19 (MeV) EG = 5.98 (MeV) SIG =  56.10 (mb)        
  * M1: ER = 10.15 (MeV) EG = 4.00 (MeV) SIG =   2.86 (mb)        
  * E2: ER = 15.59 (MeV) EG = 5.32 (MeV) SIG =   1.53 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 2) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).   
 3) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 4) Mughabghab,S.F.: "Atlas of Neutron Resonances, Fifth Edition: 
    Resonance Parameters and Thermal Cross Sections. Z=1-100",    
    Elsevier Science (2006).                                      
 5) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 6) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
 7) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
 8) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
 9) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
10) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
11) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
12) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
13) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
14) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).