20-Ca- 46

 20-CA- 46 MITSUI E.S.EVAL-APR80 M.HATCHYA                        
                      DIST-MAR02 REV3-MAY01            20010521   
----JENDL-3.3         MATERIAL 2043                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
80-04 New evaluation was made by M.Hatchya (mitsui).              
83-11 Ang. dist. was modified.                                    
84-02 Comment was added.                                          
88-10 Unchanged from JENDL-2.                                     
93-11 JENDL-3.2                                                   
       Data were mainly adopted from JENDL fusion file.           
      Compiled by T.Nakagawa                                      
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      (3,2), (3,4), (3,16), (3,17), (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 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  No resonance parameters                                 
                                                                  
      2200-m/sec cross sections and calculated resonance integrals
                     2200-m/sec      res.integ.                   
         elastic       2.900  b         -                         
         capture       0.7400 b        0.339 b                    
         total         3.640  b         -                         
                                                                  
mf=3  Neutron cross sections                                      
   Thermal region was assumed below 1.0 keV.  The capture and     
   elastic scattering cross sections were assumed to be 0.74 barns
   /5/ and 2.9 barns at 0.0253 eV, respectively.  The total cross 
   section was calculated as a sum of these two.                  
                                                                  
   For JENDL-3.2, above 1 keV, 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 cross section                                      
   The optical model calculation with casthy /10/ was adopted.    
                                                                  
     optical potential parameters were taken from ref./11/.       
               V  = 46.72         (MeV),                          
               Ws =  9.13         (MeV),                          
               Vso=  5.37         (MeV),                          
               r0 = rso = 1.26    (fm),                           
               rs = 1.39          (fm),                           
               a  = aso= 0.76     (fm),                           
               b  = 0.40          (fm).                           
                                                                  
 mt=2    Elastic scattering cross section                         
   Derived by subtracting partial cross sections from the total   
   cross section.                                                 
                                                                  
 mt=4,51-53,91 Inelastic scattering cross sections                
   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./12/ and Spear/13/.                                
                                                                  
         no.     energy(MeV)    spin-parity (direct process)      
                 0.0               0 +                            
          1      1.346             2 +          *                 
          2      2.4231            0 +                            
          3      2.5747            4 +                            
          4      2.9739            6 +                            
          5      3.0226            2 +                            
          6      3.6140            3 -          *                 
          7      3.6389            2 +                            
          8      3.8597            4 +                            
     Levels above 3.86 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.                                          
                                                                  
 mt=102  Capture cross section                                    
   Calculated with casthy /10/.                                   
                                                                  
 mt=103,107  (n,p) and (n,alpha) cross sections                   
   Statistical and pre-equilibrium model calculations using the   
   optical potential parameters for the total cross section.      
                                                                  
mf=4  Angular distributions of secondary neutrons                 
 mt=2                                                             
   Optical model calculation                                      
 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/14/.                      
                                                                  
mf=12  Photon production multiplicities                           
 mt=16, 22, 28, 51-58, 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
    (1981).                                                       
 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) Fu, C.Y.: Atomic Data and Nuclear Data Table 17, 127 (1976).  
12) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1     
    (1987)                                                        
13) Spear, R.H.: Atom. Data and Nucl. Data Table, 42, 55 (1989).  
14) Kalbach, C. : Phys. Rev. C37, 2350(1988).