20-Ca- 43

 20-CA- 43 DEC        EVAL-MAR87 M.HATCHYA(DATA ENG. CO.)         
                      DIST-SEP89 REV2-NOV93                       
----JENDL-3.2         MATERIAL 2034                               
-----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   ********************  
      (3,2), (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 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 40 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      4.160                                             
   CAPTURE     11.66                        5.798                 
   TOTAL       15.82                                              
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
   BELOW 40 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, 51-58, 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.                                                     
                                                                  
         NO.     ENERGY(MEV)    SPIN-PARITY (DIRECT PROCESS)      
        G.S.      0.0               7/2-                          
          1       0.3728            5/2-        *                 
          2       0.5934            3/2-        *                 
          3       0.9903            3/2+        *                 
          4       1.3946            5/2+        *                 
          5       1.6778           11/2-        *                 
          6       1.9018            7/2+                          
          7       1.9314            5/2-                          
          8       1.9574            1/2+                          
    LEVELS ABOVE 1.957 MEV WERE ASSUMED TO BE OVERLAPPING.  DWUCKY
    CALCULATION WAS MADE FOR THE FOLLOWING LEVELS TOO, AND RESULTS
    WERE ADDED TO THE CONTINUUM INELASTIC SCATTERING CROSS SECTION
    (MT=91).                                                      
                  2.0462            3/2-                          
                  2.2490            9/2-                          
                  2.4098            9/2+                          
                                                                  
 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                                              
   CALCULATED WITH THE CASTHY CODE/10/ AND NORMALIZED TO 22 MB    
   AT 45 KEV/11/.                                                 
                                                                  
 MT=103, 107     (N,P), (N,A)                                     
   CALCULATED WITH THE GNASH CODE/12/ USING THE OPTICAL MODEL     
   PARAMETERS LISTED IN MT=1.                                     
                                                                  
 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=51-58                                                         
   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. 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. : J. NUCL. SCI. TECH. 12, 67 (1975).               
11) MUSGROVE A.R.DE L. ET AL.: NUCL. PHYS., A279, 317 (1977).     
12) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).