20-Ca- 42

 20-CA- 42 DEC        EVAL-MAR87 M.HATCHYA(DATA ENG. CO.)         
                      DIST-MAR02 REV3-MAY01            20010521   
----JENDL-3.3         MATERIAL 2031                               
-----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   ********************  
      all cross sections except (3,102), (3,103) and (3,107)      
      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,na) and (n,np) reaction cross sections    
         (mt=16, 22, 28) were calculated by egnash2 in the        
         sincros-ii.                                              
      -  Energy distributions of secondary neutrons were replaced 
         by 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 300 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      1.222                                             
   capture      0.683                       0.3762                
   total        1.905                                             
                                                                  
mf=3  Neutron cross sections                                      
   Below 300 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)                
   This set of omp was used also for calculation of the capture,  
   (n,p), (n,a) cross section and elastic ang. distributions.     
                                                                  
 mt=2 Elastic scattering                                          
   Obtained by subtracting the sum of the partial cross sections  
   from the total cross section.                                  
                                                                  
 mt=4, 51-60, 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 '*', 
   using deformation parameters compiled by Raman et al./11/ and  
   Spear/12/.                                                     
         no.     energy(MeV)    spin-parity (direct process)      
                  0.0              0 +                            
          1       1.5246           2 +          *                 
          2       1.8373           0 +                            
          3       2.4236           2 +          *                 
          4       2.7523           4 +          *                 
          5       3.1893           6 +          *                 
          6       3.2539           4 +                            
          7       3.3000           0 +                            
          8       3.3910           2 +                            
          9       3.4464           3 -          *                 
         10       3.6530           2 +                            
   Levels above 3.653 MeV were assumed to be overlapping.         
                                                                  
 mt=16, 22, 28   (n,2n), (n,na),(n,np)                            
   Adopted from JENDL fusion file.  Theoretical calculation was   
   made with sincros-ii.                                          
                                                                  
 mt=102      Capture                                              
   Calculated with the casthy code/10/ and normalized to 12.6 mb  
   at 45 keV/13/.                                                 
                                                                  
 mt=103, 107     (n,p), (n,a)                                     
   Calculated with gnash/14/.                                     
                                                                  
 mt=203, 207  Total proton and alpha production                   
   mt=203 : sum of mt=28 and 103.                                 
   mt=207 : sum of mt=22 and 107.                                 
                                                                  
mf=4  Angular distributions of secondary neutrons                 
 mt=2                                                             
    Calculated with the casthy code/10/.                          
 mt=51-60                                                         
    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, 22, 28, 91                                                
    Based on kumabe's systematics/3/.                             
 mt=203, 207                                                      
    Based on kalbach's 1988 systematics/15/.                      
                                                                  
mf=12  Photon production multiplicities                           
 mt=16, 22, 28, 51-60, 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, 51-60, 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) Musgrove, A.R.DE L. et al.: Nucl. Phys., A279, 317 (1977).    
14) Young, P.G. and Arthur, E.D. : LA-6947 (1977).                
15) Kalbach, C. : Phys. Rev. C37, 2350(1988).