30-Zn- 70

 30-Zn- 70 JAEA       EVAL-Dec09 N.Iwamoto                        
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 3043                               
-----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 210 keV                      
      Resolved resonance parameters were taken from Mughabghab    
      /1/. The negative resonance was placed so as to             
      reproduce the cross sections at thermal energy recommended  
      by Mughabghab /1/.                                          
                                                                  
    Unresolved resonance region : 210 keV - 800 keV               
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /2/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      OPTMAN /3/ and CCONE /4/. 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           4.4289e+00                                 
       Elastic         4.3371e+00                                 
       n,gamma         9.1739e-02           1.0626e-01            
      ----------------------------------------------------------  
         (*) 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 /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= 32 (n,nd) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 51-91 (n,n') 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=104 (n,d) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /4/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
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                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /4/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /4/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /4/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,1,5 (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-70                                    
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +  *                                           
   1  0.88480   2  +  *                                           
   2  1.06830   0  +                                              
   3  1.55400   4  -                                              
   4  1.75910   2  +                                              
   5  1.78650   4  +  *                                           
   6  1.95770   2  +                                              
   7  2.14040   0  +                                              
   8  2.37500   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- 71 10.7000  1.4241  3.2699  0.7980 -0.8638  6.5518         
   Zn- 70  8.4000  2.8685  2.7953  1.0336  0.0847  9.2546         
   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         
   Cu- 70  9.5058  0.0000  2.6436  0.8098 -1.4971  4.3040         
   Cu- 69  8.9818  1.4446  2.2483  0.9050 -0.3858  6.4683         
   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         
   Ni- 69 10.0759  1.4446  2.3005  0.4505  1.7054  2.4446         
   Ni- 68  9.2928  2.9104  1.8052  0.4940  3.2390  3.9104         
   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         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Zn- 71                   
  --------------------------------------------------------        
  * 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 =  9.90 (MeV) EG = 4.00 (MeV) SIG =   2.32 (mb)        
  * E2: ER = 15.21 (MeV) EG = 5.26 (MeV) SIG =   1.44 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Mughabghab,S.F.: "Atlas of Neutron Resonances, Fifth          
     Edition: Resonance Parameters and Thermal Cross Sections.    
     Z=1-100", Elsevier Science (2006).                           
 2) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 3) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).   
 4) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 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).