30-Zn- 68

 30-Zn- 68 JAEA       EVAL-Dec09 N.Iwamoto                        
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 3037                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-12 The resolved resonance parameters were evaluated by         
      N.Iwamoto.                                                  
      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: below 110 keV                      
      Resolved resonance parameters were taken from Garg et al.   
      /1/. The negative resonance was placed so as to             
      reproduce the cross sections at thermal energy recommended  
      by Mughabghab /2/.                                          
                                                                  
    Unresolved resonance region : 110 keV - 800 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           5.6196e+00                                 
       Elastic         4.5541e+00                                 
       n,gamma         1.0655e+00           3.0917e+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 /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= 32 (n,nd) 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/.                               
                                                                  
  MT=111 (n,2p) 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= 32 (n,nd) 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: 0,1,6,8 (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 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-68                                    
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +  *                                           
   1  1.07737   2  +  *                                           
   2  1.65594   0  +                                              
   3  1.88314   2  +                                              
   4  2.33829   2  +                                              
   5  2.37030   3  +                                              
   6  2.41744   4  +  *                                           
   7  2.51020   1  +                                              
   8  2.75038   3  -  *                                           
   9  2.82158   2  +                                              
  10  2.95590   4  -                                              
  11  2.96014   3  -                                              
  12  3.00920   3  +                                              
  13  3.08120   4  -                                              
  14  3.10245   0  +                                              
  15  3.15360   3  +                                              
  16  3.16010   1  +                                              
  17  3.16400   2  -                                              
  18  3.18415   1  +                                              
  19  3.18660   2  +                                              
  20  3.28144   4  +                                              
  21  3.28709   2  +                                              
  22  3.34609   1  +                                              
  23  3.38500   0  +                                              
  24  3.40090   2  +                                              
  25  3.42504   3  -                                              
  26  3.42942   2  -                                              
  27  3.45874   5  -                                              
  28  3.48730   1  +                                              
  -------------------                                             
  *) 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- 69 10.3000  1.4446  2.6429  0.8785 -1.1966  7.2801         
   Zn- 68  9.2000  2.9104  1.9541  1.0616 -0.5162 10.3271         
   Zn- 67 10.1000  1.4660  1.8467  0.9472 -1.4178  7.9477         
   Zn- 66  9.4000  2.9542  0.7967  1.1121 -0.5948 11.1189         
   Cu- 68  8.7000  0.0000  1.7100  0.9200 -1.5524  4.8000         
   Cu- 67  8.8000  1.4660  1.4788  0.9871 -0.6304  7.2000         
   Cu- 66  8.9000  0.0000  0.9150  0.9194 -1.3650  4.6903         
   Cu- 65  8.5438  1.4884  0.5181  1.1578 -1.5153  9.2308         
   Ni- 67  9.8452  1.4660  1.4345  0.8229  0.0958  5.8000         
   Ni- 66  9.0648  2.9542  1.3371  0.9505  1.0392  8.3785         
   Ni- 65  9.4300  1.4884  1.2284  0.9166 -0.3419  6.7235         
   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         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Zn- 69                   
  --------------------------------------------------------        
  * 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 = 10.00 (MeV) EG = 4.00 (MeV) SIG =   2.52 (mb)        
  * E2: ER = 15.36 (MeV) EG = 5.28 (MeV) SIG =   1.47 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Garg,J.B. et al.: Phys. Rev. C25, 1808 (1982).                
 2) Mughabghab,S.F.: "Atlas of Neutron Resonances, Fifth          
     Edition: Resonance Parameters and Thermal Cross Sections.    
     Z=1-100", Elsevier Science (2006).                           
 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).