24-Cr- 50

 24-Cr- 50 JAEA       EVAL-Dec09 N.Iwamoto                        
                      DIST-MAY10                       20100311   
----JENDL-4.0         MATERIAL 2425                               
-----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             
    Resolved parameters for Reich-Moore formula were given in the 
      energy region below 600 keV.  Evaluation was based on the   
      experimental data of Stieglitz+71/1/, Beer+74/2/,           
      Allen+77/3/, Kenny+77/4/ and Brusegan+86/5/. Effective      
      scattering radius =5.0 fm /6/.                              
                                                                  
      Thermal cross sections and resonance integrals at 300 K     
      ----------------------------------------------------------  
                       0.0253 eV           res. integ. (*)        
                        (barn)               (barn)               
      ----------------------------------------------------------  
       Total           1.7785e+01                                 
       Elastic         2.4051e+00                                 
       n,gamma         1.5380e+01           7.2276e+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 /7/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 44 (n,n2p) cross section                                    
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /7/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /7/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /7/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /7/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /7/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /7/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /7/.                               
                                                                  
  MT=108 (n,2a) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT=111 (n,2p) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT=112 (n,pa) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
  MT=115 (n,pd) cross section                                     
    Calculated with CCONE code /7/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /7/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 44 (n,n2p) reaction                                         
    Calculated with CCONE code /7/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /7/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /7/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /7/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./8/ (+)                      
      proton   omp: Koning,A.J. and Delaroche,J.P./9/ (+)         
      deuteron omp: Lohr,J.M. and Haeberli,W./10/                 
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./11/     
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./11/     
      alpha    omp: McFadden,L. and Satchler,G.R./12/ (+)         
      (+) omp parameters were modified.                           
                                                                  
  2) Two-component exciton model/13/                              
    * Global parametrization of Koning-Duijvestijn/14/            
      was used.                                                   
    * Gamma emission channel/15/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/16/ 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/17/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of generalized Lorentzian form  
      /18/,/19/ 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 Cr-50                                    
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +                                              
   1  0.78330   2  +                                              
   2  1.88129   4  +                                              
   3  2.92450   2  +                                              
   4  3.16110   2  +                                              
   5  3.16369   6  +                                              
   6  3.32457   4  +                                              
   7  3.59455   4  +                                              
   8  3.60200   0  +                                              
   9  3.61130   4  +                                              
  10  3.62950   1  +                                              
  11  3.69200   4  +                                              
  12  3.69400   0  +                                              
  13  3.69770   2  +                                              
  14  3.79230   5  +                                              
  15  3.82540   5  +                                              
  16  3.82700   0  +                                              
  17  3.84430   4  +                                              
  18  3.85000   0  +                                              
  19  3.87490   6  +                                              
  20  3.89530   2  +                                              
  21  3.89800   4  +                                              
  22  3.93770   2  +                                              
  23  4.04000   0  +                                              
  24  4.05170   3  -                                              
  25  4.07040   2  +                                              
  26  4.12970   1  +                                              
  27  4.19290   2  +                                              
  28  4.20700   4  -                                              
  29  4.28200   1  -                                              
  30  4.35000   0  +                                              
  31  4.36300   5  -                                              
  32  4.52390   6  +                                              
  33  4.54620   3  -                                              
  34  4.65350   6  +                                              
  35  4.67600   2  +                                              
  36  4.72800   1  +                                              
  37  4.74000   0  +                                              
  38  4.74500   8  +                                              
  39  4.77200   2  +                                              
  40  4.80100   0  -                                              
  -------------------                                             
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Cr- 51  7.8300  1.6803 -1.0884  1.4788 -2.9231 13.9698         
   Cr- 50  5.7000  3.3941 -1.2177  2.0723 -3.5586 21.5750         
   Cr- 49  7.7100  1.7143 -1.4166  1.3612 -1.1260 11.2425         
    V- 50  7.0000  0.0000 -0.6353  1.4319 -3.1193  9.4496         
    V- 49  6.7530  1.7143  0.1225  1.5781 -3.1344 13.3216         
    V- 48  6.9718  0.0000 -0.7287  0.7702  0.6769  1.0000         
   Ti- 49  7.8800  1.7143  0.2445  1.1040 -0.1128  7.6316         
   Ti- 48  7.0700  3.4641  0.6643  1.4400 -0.8454 13.4405         
   Ti- 47  6.4500  1.7504  0.7264  1.5575 -2.7868 12.2959         
   Ti- 46  6.7261  3.5386  0.5488  1.5866 -1.7385 15.2474         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Cr- 51                   
  --------------------------------------------------------        
  * E1: ER = 17.80 (MeV) EG = 6.50 (MeV) SIG =  88.00 (mb)        
  * M1: ER = 11.06 (MeV) EG = 4.00 (MeV) SIG =   1.66 (mb)        
  * E2: ER = 16.99 (MeV) EG = 5.50 (MeV) SIG =   1.22 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Stiegliz,R.G. et al.: Nucl. Phys. A163, 592 (1971).           
 2) Beer,H. and Spencer,R.P.: KfK-2063 (1974), also Nucl.         
    Phys. A240, 29 (1975).                                        
 3) Allen,B.J. and Musgrove,A.R.de L.: Neutron Data of            
    Structural Materials for FBR, 1977 Geel meeting, p.447,       
    Pergamon Press (1979).                                        
 4) Kenny,M.J. et al.: AAEC/E-400 (1977).                         
 5) Brusegan,A. et al.: 85 Santa Fe vol.1 p.633 (1986).           
 6) Mughabghab,S.F. et al.: "Neutron Cross Sections", Vol.1,      
    Part A (1981).                                                
 7) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 8) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 9) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
10) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
11) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
12) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966).    
13) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
14) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
15) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
16) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
17) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
18) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
19) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).