74-W -186

 74-W -186 KHI,NEDAC  EVAL-MAR87 T.WATANABE(KHI), T.ASAMI(NEDAC)  
                      DIST-SEP89 REV2-JAN94                       
----JENDL-3.2         MATERIAL 7443                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-03 NEW EVALUATION WAS MADE FOR JENDL-3.                        
87-03 COMPILED BY T.ASAMI.                                        
94-01 JENDL-3.2.                                                  
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      ALL CROSS SECTIONS EXCEPT TOTAL                             
             THE INELASTIC SCATTERING, (N,2N), (N,3N), (N,NP),    
             (N,NA), (N,P), (N,D) AND (N,A) CROSS SECTIONS WERE   
             TAKEN FROM JENDL FUSION FILE.  FURTHER MODIFICATION  
             WAS MADE FOR THE INELASTIC SCATTERING AND CAPTURE    
             CROSS SECTIONS.                                      
      (4,16-91), (5,16-91)                                        
             THESE DATA WERE TAKEN FROM JENDL FUSION FILE.        
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL FUSION FILE /1/  (AS OF JAN. 1994)                    
            EVALUATED BY K.KOSAKO (NEDAC) AND S. CHIBA (NDC/JAERI)
            COMPILED  BY K.KOSAKO.                                
                                                                  
      DATA WERE TAKEN FROM JENDL-3.1 EXCEPT FOR THE FOLLOWING:    
      -  THE INELASTIC SCATTERING CROSS SECTIONS TO COTINUUM      
         (MT=91) WAS CALCULATED WITH CASTHY2Y AND DWUCKY IN       
         SINCROS-II SYSTEM/2/ INCLUDING CONTRIBUTIONS FROM DIRECT 
         REACTIONS.                                               
      -  THE (N,2N), (N,3N), (N,NA), (N,NP), (N,P), (N,D) AND     
         (N,A) REACTION CROSS SECTIONS (MT=16, 17, 22, 28, 103,   
         104, 107) 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.     
      -  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 12 KEV.  PARAMETERS WERE EVALUATED IN
    EXAMINING BOTH THE EXPERIMENTAL DATA/5,6,7/ AND THE           
    RECOMMENDED DATA OF BNL/8/.  FOR UNKNOWN RADIATIVE WIDTH, AN  
    AVERAGE VALUE OF 60 MILLI-EV WAS ASSUMED.  PARAMETERS FOR     
    NEGATIVE RESONANCE WERE SELECTED SO THAT THE 2200 M/S CROSS   
    SECTION FOR CAPTURE REPRODUCED GAVE A RECOMMENDED VALUE OF    
    37.8 BARNS/8/ AND GAVE A GOOD FIT TO THE EXPERIMENTAL DATA FOR
    TOTAL CROSS SECTIONS AROUND THERMAL ENERGIES.  THE SCATTERING 
    RADIUS WAS ASSUMED TO BE 7.64 FERMI/8/.  CALCULATED 2200 M/SEC
    CROSS SECTIONS AND RESONANCE INTEGRALS ARE AS FOLLOWS:        
            2200 M/S CROSS SECTION(B)     RES. INTEGRAL(B)        
    ELASTIC      0.14                                             
    CAPTURE     37.89                       347.                  
    TOTAL       38.03                                             
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
   BELOW 12 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-3.1, ABOVE 12 KEV, THE TOTAL AND PARTIAL CROSS       
   SECTIONS WERE GIVEN MAINLY BASED ON THE THEORETICAL CALCULA-   
   TIONS. THE TOTAL, ELASTIC AND INELASTIC SCATTERING, AND CAPTURE
   CROSS SECTIONS WERE CALCULATED WITH THE COUPLED-CHANNEL MODEL  
   AND THE SPHERICAL OPTICAL-STATISTICAL MODEL.  THE CALCULATIONS 
   WERE PERFORMED WITH A COMBINED PROGRAM OF CASTHY/9/ AND ECIS   
   /10/.  THE SPHERICAL OPTICAL POTENTIAL PARAMETERS USED ARE:    
         V = 48.83 - 0.0809*EN,    VSO = 5.6    (MEV)             
        WS = 6.73 - 0.0536*EN,      WV = 0      (MEV)             
         R = 1.168, RS = 1.268, RSO = 1.592     (FM)              
         A = 0.617, ASO = 0.664, B = 0.563      (FM)              
   THE DEFORMED POTENTIAL PARAMETERS WERE TAKEN FROM THE WORK OF  
   DELAROCHE/11/.                                                 
                                                                  
   FOR JENDL-3.2, ALL CROSS SECTION DATA EXCEPT FOR THE TOTAL,    
   ELASTIC SCATTERING AND CAPTURE 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 /12/ FOR PROTON, LEMOS OMP MODIFIED BY ARTHUR AND    
   YOUNG/13/ FOR ALPHA, LOHR-HAEBERLI OMP/14/ FOR DEUTERON,       
   BECCHETTII-GREENLEES OMP/15/ 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 CASTHY 
   CODE/9/. THE ABOVE-MENTIONED OMP WAS USED.  ALMOST THE SAME AS 
   JENDL-3.1.                                                     
                                                                  
 MT=2 ELASTIC SCATTERING                                          
   OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS  
   FROM THE TOTAL CROSS SECTION.                                  
                                                                  
 MT=4, 51-62, 91 INELASTIC SCATTERING                             
   THE DATA OF MT=51 TO 62 WERE CALCULATED WITH THE COMBINED      
   PROGRAM OF CASTHY /9/ AND ECIS/10/.  THESE CROSS SECTIONS IN   
   JENDL-3.2 ARE THE SAME AS JENDL-3.1 EXCEPT THAT NEW CALCULATION
   WAS MADE AT ADDITIONAL SEVERAL ENERGY POINTS.  THE CROSS       
   SECTION OF MT=91 WAS CALCULATED WITH SINCROS-II FOR JENDL      
   FUSION FILE.  THE LEVEL SCHEME WAS BASED ON REF./4/            
   CONTRIBUTIONS OF THE DIRECT PROCESS WERE CALCULATED FOR THE    
   LEVELS MARKED WITH '*'.                                        
                                                                  
       NO.  MT   ENERGY(MEV)     SPIN-PARITY (DIRECT PROCESS)     
      G.S.        0.0                 0+                          
       1    51    0.1226              2+         *                
       2    52    0.3968              4+         *                
       3    53    0.7377              2+                          
       4    54    0.8088              6+         *                
       5    55    0.8618              3+                          
       6    56    0.8820              0+                          
       7    57    0.9526              2-                          
       8    58    1.0070              2+                          
       9    59    1.0316              4+                          
      10    60    1.0452              3-                          
      11    61    1.1500              0+                          
      12    62    1.2840              2+                          
      13    62    1.2980              2+                          
      14    62    1.3220              2+                          
   LEVELS ABOVE 1.323 MEV WERE ASSUMED TO BE OVERLAPPING.  DATA   
   GIVEN IN MT=62 ARE SUM OF CROSS SECTIONS OF 12TH - 14TH LEVELS.
   THE DIRECT INELASTIC SCATTERING CROSS SECTION WAS CALCULATED   
   ALSO FOR THE LEVELS AT 1.384, 2.002, 2.588, 3.0, 3.5, 4.0, 5.0,
   5.5 AND 6.0 MEV, AND ADDED TO MT=91.                           
                                                                  
 MT=16, 17, 22, 28, 103, 104, 107                                 
        (N,2N), (N,3N), (N,NA), (N,NP), (N,P), (N,D), (N,A)       
   ADOPTED FROM JENDL FUSION FILE.  THEORETICAL CALCULATION WAS   
   MADE WITH SINCROS-II.  THE RESULTS WERE NORMALIZED TO          
        (N,2N)   2.272 B AT 14.7 MEV MEASURED BY QAIM/16/,        
                 1.9   B AT 14.  MEV MEASURED BY FREHAUT/17/,     
        (N,3N)   0.058 B AT 14.76MEV MEASURED BY FREHAUT/17/,     
        (N,P)   0.0014 B AT 14.7 MEV MEASURED BY QAIM/16/,        
  (N,D)+(N,NP) 0.00025 B AT 14.7 MEV MEASURED BY QAIM/16/,        
               0.00034 B AT 14.87MEV MEASURED BY KASUGAI/18/,     
        (N,A)  0.00076 B AT 14.87MEV MEASURED BY KASUGAI/18/,     
               0.00055 B AT 14.7 MEV MEASURED BY QAIM/16/.        
                                                                  
 MT=102      CAPTURE                                              
   CALCULATED WITH THE CASTHY CODE/9/ AND NORMALIZED TO 49+-6 MB  
   AT 500 KEV/19/.  ABOVE 3 MEV, A STRAIGHT LINE IN LOG-LOG SCALE 
   WAS ADOPTED ASSUMING 1.0 MB AT 14 MEV (BASED ON EXPERIMENTAL   
   DATA STORED IN EXFOR) FOR JENDL-3.2.                           
                                                                  
 MT=251      MU-BAR                                               
   CALCULATED WITH THE OPTICAL MODEL.                             
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
      (MT=2, 51-62: THE SAME AS JENDL-3.1)                        
 MT=2                                                             
   CALCULATED WITH THE CASTHY CODE/9/.                            
 MT=51-62                                                         
   CALCULATED WITH THE COMBINED PROGRAM OF THE CASTHY/9/ AND      
   ECIS/10/ CODES.                                                
 MT=16, 17, 22, 28, 91                                            
   TAKEN FROM JENDL FUSION FILE.                                  
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 17, 22, 28, 91                                            
   TAKEN FROM JENDL FUSION FILE.                                  
                                                                  
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) CAMARDA H.S. ET AL. : PHYS. REV. C8, 1813 (1973).             
 6) OHKUBO  M. : JAERI-M 5624 (1974).                             
 7) MACKLIN R.L. ET AL. : LA-9200-MS (1982).                      
 8) MUGHABGHAB S.F. AND GARBER D.I. :"NEUTRON CROSS SECTIONS",    
    VOL. 2, PART B (1984).                                        
 9) IGARASI S. AND FUKAHORI T.: JAREI 1321 (1991).                
10) RAYNAL J. : IAEA-SMR-9/8 P.281 (1972).                        
11) DELAROCHE J.F. ET AL. : 1979 KNOXVILLE CONF. 336 (1979).      
12) PEREY F.G.: PHYS. REV., 131, 745 (1963).                      
13) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).              
14) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS., A232, 381 (1974).     
15) BECCHETTI F.D. JR. AND GREENLEES G.W.: "POLARIZATION          
   PHENOMENA IN NUCL. REACTIONS," UNIV. WISCONSIN PRESS, P.682    
   (1971).                                                        
16) QAIM S.M. AND GRACA  C.: NUCL. PHYS., A242, 317 (1975).       
17) FREHAUT J. ET AL.: 1980 BNL SYMPOSIUM, BNL-NCS-51245, VOL. 1, 
   P.399 (1980).                                                  
18) KASUGAI Y. ET AL.: JAERI-M 93-046, P.277 (1993).              
19) VOIGNIER J. ET AL.: NUCL. SCI. ENG., 93, 43 (1986).