20-Ca- 40

 20-Ca- 40 JAEA       EVAL-JUN06 K.Shibata                        
                      DIST-MAY10                       20091228   
----JENDL-4.0         MATERIAL 2025                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
06-06 Evaluated by K.Shibata.                                     
09-12 Compiled by K.Shibata                                       
                                                                  
MF=1  General information                                         
  MT=451  Descriptive data and dictionary                         
                                                                  
MF=2  Resonance parameters                                        
  MT=151  Resolved resonance parameters                           
   The resolved resonance region remains unchanged from JENDL-3.3.
   Resolved parameters for MLBW formula were given in the energy  
   region from 1.0e-5 eV to 500 keV.  Parameters were taken from  
   the recommended data of BNL/1/ and the data for a negative     
   resonance were added so as to reproduce the recommended thermal
   cross sections for capture and scatterng/1/.  The scattering   
   radius was assumed to be 3.6 fermi.                            
                                                                  
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total           3.4685E+00                                   
     Elastic         3.0610E+00                                   
     n,gamma         4.0760E-01           2.1274E-01              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF=3  Neutron cross sections                                      
   Below 500 keV, zero background cross section was given and all 
   the cross-section data are reproduced from the evaluated       
   resolved resonance parameters with MLBW formula.               
                                                                  
   The cross sections were calcualted /2/ by using the TNG code   
   /3/.  The optilcal model parameters of Koning and Delaroche /4/
   were used for neutrons and protons.  The alpha-particle        
   potential parameters were derived from the code developed by   
   Kumar and Kailas./5/                                           
                                                                  
  MT= 1 Total                                                     
   The total cross section was taken from the JENDL-3.3 evaluation
   that was based on the experimental data of Cierjacks et al./6/ 
   and Foster, Jr. and Glasgow /7/.                               
                                                                  
  MT= 2 Elastic scattering                                        
   Obtained by subtracting the sum of the partial cross sections  
   from the total cross section.                                  
                                                                  
  MT= 4, 51-73, 91 Inelastic scattering                           
   The cross sections were calculated with the TNG code./3/       
                                                                  
  MT= 16      (n,2n)                                              
   The cross sections were calculated with the TNG code./3/       
                                                                  
  MT= 22      (n,na)                                              
   The cross sections were calculated with the TNG code./3/       
                                                                  
  MT= 28      (n,np)                                              
   The cross sections were calculated with the TNG code./3/       
                                                                  
  MT= 102     Capture                                             
   The cross sections were calculated with the TNG code./3/       
                                                                  
  MT= 103     (n,p)                                               
   The cross sections were calculated with the TNG code./3/       
                                                                  
  MT= 107     (n,a)                                               
   The cross sections were calculated with the TNG code./3/       
                                                                  
  MT= 600-649 partial (n,p) cross sections                        
   The cross sections were calculated with the TNG code./3/       
                                                                  
  MT= 800-849 partial (n,a) cross sections                        
   The cross sections were calculated with the TNG code./3/       
                                                                  
MF=4  Angular distributions of secondary neutrons                 
  MT=2                                                            
    Calculated with the TNG code/3/.                              
                                                                  
MF=6  Energy-angle distributions of secondary particles           
  MT= 16 (n,2n) reaction                                          
   Neutron and gamma-ray spectra calculated with TNG/3/.          
                                                                  
  MT= 22 (n,na) reaction                                          
   Neutron, alpha-particle, and gamma-ray spectra calculated with 
   TNG/3/.                                                        
                                                                  
  MT= 28 (n,np) reaction                                          
   Neutron, proton, and gamma-ray spectra calculated with TNG/3/. 
                                                                  
  MT= 51-73 (n,n') reaction                                       
   Neutron angular distributions and discrete gamma-ray spectra   
   calculated with TNG/3/.                                        
                                                                  
  MT= 91 (n,n') reaction                                          
   Neutron spectra, and discrete-continuous gamma-ray spectra     
   calculated with  with TNG/3/.                                  
                                                                  
  MT= 102                                                         
   Calculated with the TNG code /3/.                              
                                                                  
  MT= 600-639 (n,p) reactions leading to discrete levels          
   Proton angular distributions and discrete gamma-ray spectra    
   calculated with TNG/3/.                                        
                                                                  
  MT= 649 (n,p) reaction leading to continuum levels              
   Proton spectra and discrete-continuous gamma-ray spectra       
   calculated with TNG/3/.                                        
                                                                  
  MT= 800-832 (n,a) reactions leading to discrete levels          
   Alpha-particle angular distributions and gamma-ray spectra     
   calculated with TNG/3/.                                        
                                                                  
  MT= 849 (n,a) reaction leading to continuum levels              
   Alpha-particle spectra and discrete-continuous gamma-ray       
   spectra calculated with TNG/3/.                                
                                                                  
< Appendix >                                                      
******************************************************************
*            Nuclear Model Calcualtions with TNG Code /3/        *
******************************************************************
The description of the model calculations is given in Ref.2.      
                                                                  
< Optical model parameters >                                      
Neutron and protons:                                              
  Koning and Delaroche /4/                                        
Alphas:                                                           
  The potential parameters were obtained using the code developed 
  by Kumar and Kailas./5/                                         
                                                                  
< Level scheme of Ca- 40 >                                        
  -------------------------                                       
   No.   Ex(MeV)     J  PI                                        
  -------------------------                                       
    0    0.00000     0   +                                        
    1    3.35260     0   +                                        
    2    3.73670     3   -                                        
    3    3.90440     2   +                                        
    4    4.49140     5   -                                        
    5    5.21160     0   +                                        
    6    5.24880     2   +                                        
    7    5.27880     4   +                                        
    8    5.61350     4   -                                        
    9    5.62940     2   +                                        
   10    5.90260     1   -                                        
   11    6.02550     2   -                                        
   12    6.02970     3   +                                        
   13    6.28520     3   -                                        
   14    6.42240     2   +                                        
   15    6.50790     4   +                                        
   16    6.54280     4   +                                        
   17    6.58250     3   -                                        
   18    6.75040     2   -                                        
   19    6.90870     2   +                                        
   20    6.93020     6   +                                        
   21    6.93130     3   -                                        
   22    6.93800     3   -                                        
   23    6.95050     1   -                                        
                                                                  
The direct-reaction process was taken into account for the 2nd,   
3rd, 4th, 6th, 7th, 9th, 13th, 14th, 15th, 17th, and 19th levels  
by DWBA.                                                          
                                                                  
< Level density parameters >                                      
Energy dependent parameters of Mengoni-Nakajima /8/ were used.    
  ----------------------------------------------------------      
  Nuclei    a*    Pair    Esh     T     E0    Ematch Econt        
          1/MeV   MeV     MeV    MeV    MeV    MeV    MeV         
  ----------------------------------------------------------      
  Ca- 41   6.285  1.874 -0.149  1.397 -0.507  9.227  4.728        
  Ca- 40   5.998  3.795 -1.846  1.494  2.450 10.045  7.113        
  Ca- 39   6.455  1.922 -0.346  0.839  3.517  8.268  4.920        
  K - 40   6.010  0.000 -0.027  1.352 -1.491  6.250  3.557        
  K - 39   5.593  1.922 -0.694  1.476  0.637  8.268  5.502        
  Ar- 37   6.197  1.973 -0.393  1.348  0.521  8.189  5.213        
  Ar- 36   5.504  4.000 -1.321  1.645  1.856 11.777  7.423        
  ----------------------------------------------------------      
                                                                  
References                                                        
 1) Mughaghab S.F. et al.:"Neutron Cross Sections", Vol. 1, Part  
    A (1981).                                                     
 2) Shibata, K: J. Nucl. Sci. Technol., 44, 10 (2007).            
 3) Fu, C.Y.: ORNL/TM-7042 (1980); Shibata, K., Fu, C.Y.: ORNL/TM-
    10093.                                                        
 4) Koning, A.J., Delaroche, J.P.: Nucl. Phys., A713, 231 (2003). 
 5) Kumar, A., Kailas, S: a computer code contained in RIPL-2,    
    private communication (2002).                                 
 6) Cierjacks, S. et al.: KFK-1000 (1968).                        
 7) Foster, D.G, Glasgow, D.W.: Phys. Rev. C3, 576 (1971).        
 8) Mengoni, A., Nakajima, Y. Nucl. Sci. Technol., 31, 151 (1994).