20-Ca- 44

 20-CA- 44 DEC        EVAL-MAR87 M.HATCHYA(DATA ENG. CO.)         
                      DIST-MAR02 REV3-MAY01            20010521   
----JENDL-3.3         MATERIAL 2037                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
87-03 New evaluation was made to give a full revision for JENDL-2 
      data.                                                       
87-03 Compiled by T.Asami(nedac)                                  
93-11 JENDL-3.2                                                   
       Data were mainly adopted from JENDL fusion file.           
      Compiled by T.Nakagawa                                      
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      (3,1), (3,2), (3,4), (3,16), (n,3n), (3,22), (3,28),        
      (3,51-91)                                                   
      all angular distributions except for (4,2).                 
      all energy distributions.                                   
     ***********************************************************  
     -------------------------------------------------------------
      JENDL fusion file /1/  (as of Nov. 1993)                    
            Evaluated by K.Kosako (nedac) and S.Chiba (ndc/jaeri) 
            Compiled  by K.Kosako.                                
                                                                  
      -  The inelastic scattering cross sections and angular      
         distributions of inelastically scattered neutrons (except
         continuum inelastic) were calculated with casthy2y and   
         dwucky in sincros-ii system/2/ including contributions   
         from direct reactions.                                   
      -  The (n,2n), (n,3n), (n,na) and (n,np) reaction cross     
         sections (mt=16, 17, 22, 28) were calculated by egnash2  
         in the sincros-ii.                                       
      -  Energy distributions of secondary neutrons were replaced 
         with those calculated by egnash2.  The ddx's of the      
         continuum neutrons were calculated by Kumabe's systema-  
         tics /3/ using f15tob /1/.  The precompound/compound     
         ratio was calculated by the sincros-ii code system.      
      -  The resonance parameters, total, capture, (n,p) and (n,a)
         cross sections and ang. Distributions of elastically     
         scattered neutrons were taken from JENDL-3.1.            
      -  Optical-model, level density and other parameters used in
         the sincros-ii calculation are described in ref./2/.     
         Level schemes were determined on the basis of ENSDF/4/.  
     -------------------------------------------------------------
2001-05 JENDL-3.3                                                 
        Gamma-ray production date were evaluated and compiled by  
        K.Shibata (jaeri/ndc).                                    
        ********  modified parts for JENDL-3.3  ******************
        (1,451)           Updated.                                
        (3,203), (3,207)  Calculated.                             
        (3,251)           Deleted.                                
        (4,2)             Transformation matrix deleted.          
        (4,16-91)         Deleted.                                
        (5,16-91)         Deleted.                                
        (6,16-207)        Taken form JENDL fusion file.           
        (12,16-107)       Evaluated.                              
        (14,16-107)       Evaluated.                              
        (15,16-107)       Evaluated.                              
        **********************************************************
                                                                  
                                                                  
mf=1  General information                                         
 mt=451  Descriptive data and dictionary                          
                                                                  
mf=2  Resonance parameters                                        
 mt=151  Resolved resonance parameters                            
   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/5/ and the data for a negative     
   resonance were added so as to reproduce the recommended thermal
   cross sections for capture and scattering/5/.  The scattering  
   radius was assumed to be 3.6 fermi.  Calculated 2200 m/sec     
   cross sections and resonance integrals are as follows:         
                                                                  
           2200 m/s cross section(b)     res. integral(b)         
   elastic      3.320                                             
   capture      0.888                       0.4254                
   total        4.208                                             
                                                                  
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.               
                                                                  
   For JENDL-3.2, all cross-section data except for the total,    
   capture, (n,p) and (n,a) cross sections were adopted from JENDL
   fusion file.  The calculation was made with sincros-ii system  
   /2/ by adopting walter-guss omp modified by Yamamuro/2/ for    
   neutron, Perey omp /6/ for proton, Lemos omp modified by Arthur
   and Young/7/ for alpha, Lohr-Haeberli omp/8/ for deuteron,     
   Becchettii-Greenlees omp/9/ for triton and he-3, and standard  
   level density parameters of sincros-ii system.                 
                                                                  
 mt=1 Total                                                       
   Optical and statistical model calculation was made with the    
   casthy code/10/. the optical potential parameters used are:    
         V = 49.68,                Vso = 7.12   (MeV)             
        Ws = 7.76 - 0.5*En,         Wv = 0      (MeV)             
         r = 1.17,   rs = 1.09,    rso = 1.17   (fm)              
         a = 0.6,   aso = 0.6,       b = 0.69   (fm)              
                                                                  
 mt=2 Elastic scattering                                          
   Obtained by subtracting the sum of the partial cross sections  
   from the total cross section.                                  
                                                                  
 mt=4, 51-59, 91 Inelastic scattering                             
   The cross sections were taken from JENDL fusion file.  The     
   level scheme was based on ref./4/  Contributions of the direct 
   process were calculated for the levels marked with '*' by means
   of dwucky.  Deformation parameters were adopted from Raman et  
   al./11/ and Spear/12/.                                         
                                                                  
         no.     energy(MeV)    spin-parity (direct process)      
                 0.0               0 +                            
         1       1.157             2 +          *                 
         2       1.8835            0 +                            
         3       2.2831            4 +          *                 
         4       2.6565            2 +          *                 
         5       3.0443            4 +          *                 
         6       3.2849            5 +                            
         7       3.3013            2 +                            
         8       3.3079            3 -          *                 
         9       3.3572            2 +                            
    Levels above 3.357 MeV were assumed to be overlapping.        
                                                                  
 mt=16, 17, 22, 28   (n,2n), (n,3n), (n,na),(n,np)                
   Adopted from JENDL fusion file.  Theoretical calculation was   
   made with sincros-ii.  The (n,np) cross section was normalized 
   to the experimental data of Ikeda et al./13/                   
                                                                  
 mt=102      Capture                                              
   Calculated with the casthy code/10/ and normalized to 7.1 mb   
   at 45 keV/14/.                                                 
                                                                  
 mt=103, 107    (n,p), (n,a)                                      
   Calculated with the gnash code/15/ using the same optical model
   parameters as the total cross section.                         
                                                                  
mf=4  Angular distributions of secondary neutrons                 
 mt=2                                                             
   Calculated with the casthy code/10/.                           
 mt=51-58                                                         
   Taken from JENDL fusion file.  Calculated with the casthy and  
   dwucky in the sincros-ii system.                               
                                                                  
mf=6  Energy-angle distributions of secondary particles           
 mt=16, 17, 22, 28, 91                                            
    Based on kumabe's systematics/3/.                             
 mt=203, 207                                                      
    Based on kalbach's 1988 systematics/16/.                      
                                                                  
mf=12  Photon production multiplicities                           
 mt=16, 22, 28, 51-59, 91, 103, 107                               
    Calculated with the egnash code/2/.                           
 mt=102                                                           
    Calculated with the casthy code/10/.                          
                                                                  
mf=14  Photon angular distributions                               
 mt=16, 22, 28, 51-59, 91, 102, 103, 107                          
   Assumed to be isotropic in the laboratory system.              
                                                                  
mf=15  Continuous photon energy spectra                           
 mt=16, 22, 28, 91, 103, 107                                      
   Calculated with the egnash code/2/.                            
 mt=102                                                           
   Calculated with the casthy code /10/.                          
                                                                  
                                                                  
References                                                        
 1) Chiba, S. et al.: JAERI-M 92-027, p.35 (1992).                
 2) Yamamuro, N.: JAERI-M 90-006 (1990).                          
 3) Kumabe, I. et al.: Nucl. Sci. Eng., 104, 280 (1990).          
 4) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.       
 5) Mughabghab S.F., et al. :"Neutron Cross Sections",            
    Vol. 1, Part A (1984).                                        
 6) Perey, F.G.: Phys. Rev., 131, 745 (1963).                     
 7) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980).              
 8) Lohr, J.M. and Haeberli, W.: Nucl. Phys., A232, 381 (1974).   
 9) Becchetti, F.D. Jr. and Greenlees, G.W.: "Polarization        
   Phenomena in Nucl. Reactions," Univ. Wisconsin Press, p.682    
   (1971).                                                        
10) Igarasi, S. and Fukahori, T.: JAERI 1321 (1991).              
11) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1     
    (1987)                                                        
12) Spear, R.H.: Atom. Data and Nucl. Data Table, 42, 55 (1989).  
13) Ikeda, Y. et al.: JAERI 1312 (1988).                          
14) Musgrove A.R.DE L. et al.: Nucl. Phys., A279, 317 (1977).     
15) Young, P.G. and Arthur, E.D. : LA-6947 (1977).                
16) Kalbach, C. : Phys. Rev. C37, 2350(1988).