23-V - 51

 23-V - 51 JAEA       EVAL-Mar10 N.Iwamoto                        
                      DIST-MAY10                       20100312   
----JENDL-4.0         MATERIAL 2328                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
10-03 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 (Reich-Moore formula) : below 100.0 
      keV. Parameters were evaluated based on experimental data   
      /1,2,3,4,5/ and modified to reproduce experimental          
      total cross sections. The negative resonance was placed so  
      as to reproduce the cross sections at thermal energy        
      recommended by Mughabghab /4/.                              
                                                                  
      Thermal cross sections and resonance integrals at 300 K     
      ----------------------------------------------------------  
                       0.0253 eV           res. integ. (*)        
                        (barn)               (barn)               
      ----------------------------------------------------------  
       Total           9.8868e+00                                 
       Elastic         4.9677e+00                                 
       n,gamma         4.9191e+00           2.5607e+00            
      ----------------------------------------------------------  
         (*) Integrated from 0.5 eV to 10 MeV.                    
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    In the energy range from 0.1 to 5 MeV, cross section was      
      adopted from JENDL-3.3. Above 5 MeV, cross section was      
      calculated with CCONE code/6/.                              
                                                                  
  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 /6/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /6/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /6/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /6/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=111 (n,2p) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT=112 (n,pa) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    The Legendre coefficients were taken from JEFF-3.1, taking    
      into account the result of a benchmark test.                
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /6/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /6/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /6/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./7/                          
      proton   omp: Koning,A.J. and Delaroche,J.P./8/ (+)         
      deuteron omp: Lohr,J.M. and Haeberli,W./9/                  
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./10/ (+) 
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./10/     
      alpha    omp: Huizenga,J.R. and Igo,G./11/ (+)              
      (+) omp parameters were modified.                           
                                                                  
    * DWBA calculation                                            
           levels: 2,3,4 (see Table 1)                            
                                                                  
  2) Two-component exciton model/12/                              
    * Global parametrization of Koning-Duijvestijn/13/            
      was used.                                                   
    * Gamma emission channel/14/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/15/ 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/16/.           
      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 V-51                                     
  ---------------------------------                               
  No.  Ex(MeV)  J  PI,   DWBA: beta                               
  ---------------------------------                               
   0  0.00000  7/2 -                                              
   1  0.32008  5/2 -                                              
   2  0.92866  3/2 -           0.06                               
   3  1.60923 11/2 -           0.07                               
   4  1.81324  9/2 -           0.07                               
   5  2.41078  3/2 -                                              
   6  2.54740  1/2 +                                              
   7  2.67743  3/2 +                                              
   8  2.69962 15/2 -                                              
   9  2.79000  5/2 -                                              
  10  3.08362  5/2 -                                              
  11  3.15000  3/2 -                                              
  12  3.21480  3/2 -                                              
  13  3.26403  5/2 -                                              
  14  3.27999  5/2 -                                              
  15  3.31000  5/2 +                                              
  16  3.32000  5/2 -                                              
  17  3.37200  3/2 -                                              
  18  3.37772  9/2 -                                              
  19  3.38110  3/2 -                                              
  20  3.38320  9/2 +                                              
  21  3.38558 13/2 -                                              
  22  3.39502 13/2 -                                              
  23  3.41220  7/2 +                                              
  24  3.44392  5/2 +                                              
  25  3.45409  9/2 -                                              
  26  3.51702  9/2 -                                              
  27  3.55480  9/2 -                                              
  28  3.56260  5/2 -                                              
  29  3.56820  7/2 -                                              
  30  3.57663  3/2 -                                              
  31  3.61405  9/2 -                                              
  32  3.62370  5/2 +                                              
  33  3.63200  3/2 +                                              
  34  3.63203  5/2 -                                              
  35  3.66310  3/2 -                                              
  36  3.66800  3/2 -                                              
  37  3.67780  3/2 -                                              
  38  3.68300  5/2 -                                              
  39  3.72270  5/2 -                                              
  40  3.74300  1/2 +                                              
  ---------------------------------                               
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
    V- 52  7.5500  0.0000 -0.6140  1.1810 -1.6043  6.2628         
    V- 51  6.9100  1.6803 -0.6457  1.5183 -2.1580 12.5084         
    V- 50  7.0000  0.0000 -0.6353  1.4319 -3.1193  9.4496         
   Ti- 51  6.8200  1.6803 -0.3127  1.1927  0.5191  7.0839         
   Ti- 50  7.2500  3.3941 -0.4613  1.2919  1.1007 10.9863         
   Ti- 49  7.8800  1.7143  0.2445  1.1040 -0.1128  7.6316         
   Sc- 50  7.2083  0.0000 -0.8027  1.2352 -1.5662  6.4725         
   Sc- 49  6.7530  1.7143 -0.4669  1.1948  0.6746  6.9625         
   Sc- 48  7.3300  0.0000  0.2130  1.1004 -1.3101  5.1281         
   Sc- 47  6.5239  1.7504  1.5602  1.4579 -2.4909 11.0454         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for  V- 52                   
  --------------------------------------------------------        
  * E1: ER = 19.02 (MeV) EG = 7.21 (MeV) SIG =  81.49 (mb)        
  * M1: ER = 10.98 (MeV) EG = 4.00 (MeV) SIG =   8.28 (mb)        
  * E2: ER = 16.88 (MeV) EG = 5.49 (MeV) SIG =   1.10 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Brusegan,A. et al.: Neutron Total Cross Section of            
    Vanadium, 97Trieste 410,(1997).                               
 2) Winters,R.R. et al.: Phys. Rev. C18, 2092 (1978).             
 3) Garg,J.B. et al.: Nucl. Sci. Eng. 65, 76 (1978).              
 4) Mughabghab,S.F. et al.: "Neutron Cross Sections Vol.1 Part A" 
    Academic Press (1981).                                        
 5) Macklin,R.L. et al.: Nucl. Sci. Eng. 78, 110 (1981).          
 6) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 7) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 8) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
 9) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
10) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
11) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
12) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
13) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
14) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
15) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
16) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).