21-Sc- 45

 21-SC- 45 KHI        EVAL-AUG88 T.WATANABE                       
                      DIST-SEP89 REV2-SEP93                       
----JENDL-3.2         MATERIAL 2125                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
88-08  JENDL-2 MODIFIED BY T.WATANABE                             
                          (KAWASAKI HEAVY INDUSTRIES, LTD.)       
93-09  JENDL-3.2.                                                 
       COMPILED BY T.NAKAGAWA (NDC/JAERI)                         
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (2,151)              PARAMETERS OF 3.295-KEV RESONANCE      
      (3,2), (3,102)                                              
     ***********************************************************  
                                                                  
MF=1    GENERAL INFORMATION                                       
  MT=451   DESCRIPTIVE DATA AND DICTIONARY                        
                                                                  
MF=2                                                              
  MT=151   RESONANCE PARAMETERS            : 1.0E-5 EV - 100 KEV  
        RESOLVED RESONANCES FOR MLBW FORMULA:                     
           PARAMETERS WERE EVALUATED BASED ON EXPERIMENTAL DATA   
           /1/,/2/,/3/ AND MODIFIED TO REPRODUCE EXPERIMENTAL     
           TOTAL CROSS SECTIONS. NEGATIVE ENERGY LEVELS WERE ADDED
           TO REPRODUCE THE TOTAL AND CAPTURE CROSS SECTIONS/4/ AT
           THERMAL AND THE TOTAL CROSS SECTION /5/ AT 2 KEV.  FOR 
           JENDL-3.2, CAPTURE WIDTH OF 3.295-KEV RESONANCE WAS    
           CHANGED TO 0.71 EV/4/.                                 
                                                                  
        CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS
                        2200 M/SEC        RES. INTEG.             
            ELASTIC       22.48 B              -                  
            CAPTURE       27.14 B            11.85 B              
            TOTAL         49.62 B              -                  
                                                                  
MF=3    NEUTRON CROSS SECTIONS                    : ABOVE 100 KEV 
  MT=1,2,4,51-74,91,102  TOTAL, ELASTIC, INELASTIC AND CAPTURE    
           CALCULATED WITH OPTICAL AND STATISTICAL MODEL.  DIRECT 
           INELASTIC REACTION CROSS SECTIONS WERE EVALUATED WITH  
           DWBA /6/ AND ADDED TO COMPOUND PROCESSES.  STATISTICAL 
           MODEL CALCULATION WITH CASTHY CODE /7/ WAS PERFORMED.  
           MT=102 CAPTURE CROSS SECTION WAS NORMALIZED TO THE     
           EXPERIMENTAL DATA OF VOIGNIER+/8/, 11.2 MB AT 500 KEV. 
           DIRECT CAPTURE CROSS SECTION WAS CALCULATED FROM A     
           SIMPLE FORMULA OF BENZI AND REFFO/9/ AND NORMALIZED TO 
           1.0 MB AT 14.0 MEV.                                    
                                                                  
        THE SPHERICAL OPTICAL POTENTIAL PARAMETERS WERE EVALUATED 
           TO REPRODUCE TOTAL EXPERIMENTAL CROSS SECTIONS         
           /10,11,12/.                                            
           V = 56.2 - 0.3244*EN  MEV  R0= 1.155 FM  A0= 0.666 FM  
           WS= 8.638-0.003093*EN MEV  RS= 1.473 FM  B = 0.262 FM  
           VSO=5.254 MEV              RSO=1.003 FM  ASO=0.485 FM  
                                                                  
        THE LEVEL SCHEME TAKEN FROM REF./13/:                     
           NO.        ENERGY(MEV)   SPIN-PARITY     BETA          
           G.S        0.0            7/2-                         
            1         0.012396       3/2+                         
            2         0.37659        3/2-           0.108         
            3         0.543          5/2+                         
            4         0.72017        5/2-           0.0867        
            5         0.9392         1/2+           0.0211        
            6         0.97461        7/2+                         
            7         1.0672         3/2-           0.0586        
            8         1.23723       11/2-           0.143         
            9         1.30342        3/2+                         
           10         1.40887        7/2-                         
           11         1.43367        9/2+                         
           12         1.5564         3/2-                         
           13         1.66231        9/2-           0.0843        
           14         1.8004         5/2+                         
                                                                  
        CONTINUUM LEVELS ASSUMED ABOVE 1.9 MEV                    
           LEVEL DENSITY PARAMETERS WERE EVALUATED USING D0/4/,   
           AND LEVEL DATA /13/.                                   
                      A          T          EX         SIG**2(0)  
           21-SC-45   7.855      1.282     10.08       7.602      
           21-SC-46   7.231      1.268      7.328      7.867      
                                                                  
  MT=16  (N,2N)                                                   
           THE JENDL-2 DATA WERE MODIFIED BY USING EXPERIMENTAL   
           DATA /14/.                                             
  MT=103 (N,P)                                                    
           TAKEN FROM COMPILATION BY ALLEY AND LESSLER /15/       
  MT=107 (N,ALPHA)                                                
           SAME AS MT=103, BUT SLIGHTLY MODIFIED TO REPRODUCE     
           EXPERIMENTAL DATA/14/.                                 
  MT=251 MU-BAR                                                   
           CALCULATED FROM THE DATA IN MF=4.                      
                                                                  
MF=4    ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               
  MT=2     CALCULATED WITH OPTICAL MODEL.                         
  MT=51-91 CALCULATED WITH HAUSER-FESHBACH FORMULA ADDED WITH     
           DIRECT REACTION.                                       
  MT=16    ISOTROPIC IN THE LABORATORY SYSTEM                     
                                                                  
MF=5    ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
           CALCULATED WITH SINCROS /16/.                          
                                                                  
REFERENCES                                                        
 1) LIOU, H.I. ET AL.: NUCL. SCI. ENG. 67, 326 (1978).            
 2) KENNY, M.J. ET AL.: AUSTRALIAN J. PHYS. 30, 605 (1977).       
 3) ALLEN, B.J. ET AL.: NUCL. SCI. ENG. 82, 230 (1982).           
 4) MUGHABGHAB, S.F., ET AL: 'NEUTRON CROSS SECTIONS VOL.1 PART A'
    ACADEMIC PRESS (1981)                                         
 5) FUJITA, Y: J. NUCL. SCI. TECHNOL. 20, 191 (1983).             
 6) KUNZ, P.D.: UNPUBLISHED (1974).                               
 7) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).              
 8) VOIGNIER, J, ET AL.: NUCL. SCI. ENG. )3, 43 (1986). DATA WERE 
    TAKEN FROM EXFOR                                              
 9) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).                   
10) POENITZ, W.P. AND WHALEN, J.F.: ANL/NDM-80 (1983).            
11) BARNARD, E. ET AL.: Z. PHYS. 245, 36 (1971).                  
12) FOSTER, JR. D.G. AND GLASGOW D.W.: PHYS. REV. C3, 576 (1971). 
13) BURROWS, T.W.: NUCLEAR DATA SHEETS 40, 216 (1983).            
14) IKEDA, Y., ET AL.: JAERI 1312 (1988).                         
15) ALLEY, W.E. AND LESSLER, R.M: NUCLEAR DATA TABLES A11,648     
    (1973).                                                       
16) YAMAMURO, N.: JAERI-M 88-140 (1988).