20-Ca- 48

 20-CA- 48 DEC        EVAL-MAR87 M.HATCHYA(DATA ENG. CO.)         
                      DIST-SEP89 REV2-NOV93                       
----JENDL-3.2         MATERIAL 2049                               
-----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), (3,17), (3,28), (3,51-91),     
      (3,103).                                                    
           (3,22), (3:53-58): DELETED                             
      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) AND (N,NP) REACTION CROSS SECTIONS    
         (MT=16, 17, 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/.  
     -------------------------------------------------------------
                                                                  
                                                                  
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      3.717                                             
   CAPTURE      1.092                       0.4859                
   TOTAL        4.809                                             
                                                                  
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)              
   THE SHAPE OF THE TOTAL CROSS SECTION WAS SLIGHTLY MODIFIED     
   FOR JENDL-3.2.                                                 
                                                                  
 MT=2 ELASTIC SCATTERING                                          
   OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS  
   FROM THE TOTAL CROSS SECTION.                                  
                                                                  
 MT=4, 51-52, 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       3.8317           2 +          *                 
          2       4.2842           0 +                            
   LEVELS ABOVE 4.284 MEV WERE ASSUMED TO BE OVERLAPPING.  THE    
   LEVELS FOR MTS=53 TO 58 GIVEN IN JENDL-3.1 WERE NOT CONSIDERED 
   IN JENDL FUSION FILE.  THE DIRECT INELSTIC CROSS SECTION TO THE
   LEVELS AT 4.507 MEV WAS CALCULATED WITH DWUCKY AND ADDED TO THE
   CONTINUUM INELASTIC CROSS SECTION (MT=91).                     
                                                                  
 MT=16, 17, 28   (N,2N), (N,3N), (N,NP)                           
   ADOPTED FROM JENDL FUSION FILE.  THEORETICAL CALCULATION WAS   
   MADE WITH SINCROS-II.  THE (N,2N) CROSS SECTION WAS NORMALIZED 
   TO THE EXPERIMENTAL DATA OF IKEDA ET AL./13/ (0.759 B AT 13.99 
   MEV)                                                           
                                                                  
 MT=103, 107    (N,P), (N,A)                                      
   CALCULATED WITH THE GNASH CODE/14/ USING THE OPTICAL MODEL     
   PARAMETERS LISTED AT MT=1.  THE (N,P) CROSS SECTIONS WERE      
   NORMALIZED TO THE EXPERIMENTAL DATA OF TIWARI ET AL./15/ AT    
   14.5 MEV. THE SHAPE OF (N,P) CROSS SECTION AROUND THE THRESHOLD
   ENERGY WAS CHANGED FOR JENDL-3.2.                              
                                                                  
 MT=102      CAPTURE                                              
   CALCULATED WITH THE CASTHY CODE/10/ AND NORMALIZED TO 1.05 MB  
   AT 30 KEV/16/.                                                 
                                                                  
 MT=251      MU-BAR                                               
   CALCULATED WITH THE OPTICAL MODEL.                             
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2                                                             
   CALCULATED WITH THE CASTHY CODE/10/.                           
 MT=51-52                                                         
   TAKEN FROM JENDL FUSION FILE.  CALCULATED WITH THE CASTHY AND  
   DWUCKY IN THE SINCROS-II SYSTEM.                               
 MT=16, 17, 28, 91                                                
   TAKEN FROM JENDL FUSION FILE, AND TRANSFORMED INTO THE LAB     
   SYSTEM.                                                        
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 17, 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. AND GARBER D.I. :"NEUTRON CROSS SECTIONS",    
    VOL. 1, PART B (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) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).                  
15) TIWARI P.N. ET AL. : PHYS. REV. 167, 1091 (1968).             
16) CARTON R.F. ET AL.: NUCL. PHYS., A465, 274 (1987).