74-W -183

 74-W -183 KHI,NEDAC  EVAL-MAR87 T.WATANABE(KHI), T.ASAMI(NEDAC)  
                      DIST-SEP89 REV2-JAN94                       
----JENDL-3.2         MATERIAL 7434                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-03 NEW EVALUATION WAS MADE FOR JENDL-3.                        
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 2.2 KEV.  PARAMETERS WERE EVALUATED BY
   EXAMINING BOTH THE EXPERIMENTAL DATA/5,6,7/ AND THE RECOMMENDED
   DATA OF BNL/8/.  FOR UNKNOWN RADIATIVE WIDTH, AN AVERAGE VALUE 
   OF 55 MILLI-EV WAS ASSUMED.  PARAMETERS FOR A NEGATIVE         
   RESONANCE WERE SELECTED SO THAT THE 2200 M/S CROSS SECTION FOR 
   CAPTURE REPRODUCED GAVE A RECOMMENDED VALUE OF 10.2 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 7.3 FM.  CALCULATED 2200 M/SEC CROSS SECTIONS AND
   RESONANCE INTEGRALS ARE AS FOLLOWS:                            
                                                                  
           2200 M/S CROSS SECTION(B)     RES. INTEGRAL(B)         
   ELASTIC        2.38                                            
   CAPTURE       10.11                      335.                  
   TOTAL         12.49                                            
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
   BELOW 2.2 KEV, ZERO BACKGROUND CROSS SECTION WAS GIVEN AND ALL 
   THE CROSS-SECTION DATA ARE REPRODUCED FROM THE EVALUATED       
   RESONANCE PARAMETERS WITH MLBW FORMULA.                        
                                                                  
   FOR JENDL-3.1, ABOVE 2.2 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                                                       
   CALCULATED WITH THE COMBINED PROGRAM OF THE ECIS AND CASTHY    
   CODES.  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, 51-60, 91 INELASTIC SCATTERING                             
   THE DATA OF MT=51 TO 60 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              1/2 -                          
       1    51    0.0465           3/2 -         *                
       2    52    0.0991           5/2 -         *                
       3    53    0.2070           7/2 -         *                
       4    54    0.2088           3/2 -                          
       5    55    0.2917           5/2 -                          
       6    56    0.3089           9/2 -         *                
       7    57    0.3095          11/2 +                          
       8    58    0.4121           7/2 -                          
       9    58    0.4530           7/2 -                          
      10    59    0.4870          13/2 +                          
      11    59    0.5330           1/2 +                          
      12    60    0.5500           9/2 -                          
      13    60    0.5953           9/2 -                          
      14    60    0.6228           9/2 +                          
   LEVELS ABOVE 0.624 MEV WERE ASSUMED TO BE OVERLAPPING.  DATA OF
   LEVELS 8-9, 10-11 AND 12-14 WERE LUMPED AS IS INDICATED IN THE 
   ABOVE TABLE.  THE DIRECT INELASTIC SCATTERING CROSS SECTION WAS
   CALCULATED ALSO FOR THE LEVELS AT 0.904, 0.935, 1.025, 1.485,  
   1.866, 2.127, 2.505, 2.912, 3.404, 4.0, 4.5, 5.0 AND 5.5 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)   2.150 B AT 14.7 MEV (SYSTEMATICS OF QAIM/16/),   
        (N,P)   0.0041 B AT 14.7 MEV MEASURED BY QAIM/16/,        
   (N,D)+(N,NP) 0.0013 B AT 14.7 MEV MEASURED BY QAIM/16/,        
        (N,A)   0.0018 B AT 14.7 MEV (SYSTEMATICS OF QAIM/16/).   
                                                                  
 MT=102      CAPTURE                                              
   CALCULATED WITH THE CASTHY CODE/9/ AND NORMALIZED TO 70+-9 MB  
   AT 500 KEV/17/.  ABOVE 3 MEV, A STRAIGHT LINE IN LOG-LOG SCALE 
   WAS ADOPTED ASSUMING 1.0 MB AT 14 MEV FOR JENDL-3.2.           
                                                                  
 MT=251      MU-BAR                                               
   CALCULATED WITH THE OPTICAL MODEL.                             
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
      (MT=2, 51-60: THE SAME AS JENDL-3.1)                        
 MT=2                                                             
   CALCULATED WITH THE CASTHY CODE/9/.                            
 MT=51-60                                                         
   CALCULATED WITH THE COMBINED PROGRAM OF 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) VOIGNIER J. ET AL.: NUCL. SCI. ENG., 93, 43 (1986).