20-Ca- 46

 20-CA- 46 MITSUI E.S.EVAL-APR80 M.HATCHYA                        
                      DIST-FEB84 REV2-NOV93                       
----JENDL-3.2         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/.  
     -------------------------------------------------------------
                                                                  
                                                                  
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.      
                                                                  
 MT=251  MU-BAR                                                   
   CALCULATED WITH OPTICAL MODEL.                                 
                                                                  
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.                               
 MT=16, 17, 22, 28, 91                                            
   TAKEN FROM JENDL FUSION FILE, AND TRANSFORMED INTO THE LAB     
   SYSTEM.                                                        
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 17, 22, 28, 91                                            
   TAKEN FROM JENDL FUSION FILE, AND TRANSFORMED INTO THE LAB     
   SYSTEM.                                                        
                                                                  
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).