19-K - 39

 19-K - 39 FUJI E.C.  EVAL-MAY87 H.NAKAMURA                       
                      DIST-SEP89 REV2-FEB94                       
----JENDL-3.2         MATERIAL 1925                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-05  NEWLY EVALUATED BY H.NAKAMURA (FUJI ELECTRIC CO. LTD.)     
94-02  JENDL-3.2                                                  
       TOTAL CROSS SECTION WAS CALCULATED BY T. WATANABE (KHI).   
       INELASTIC SCATTERING CROSS SECTIONS WERE CALCULATED BY     
       K.SHIBATA (JAERI).                                         
       DATA WERE COMPILED BY K.SHIBATA.                           
*****  MODIFIED PARTS FOR JENDL-3.2 ****************************  
(3,1),(3,4),(3,51-91),(3,251),(4,2),(4,51-54)                     
              NEW OPTICAL AND STATISTICAL MODEL CAL.              
(3,2)         TOTAL - NONELASTIC                                  
****************************************************************  
MF=1  GENERAL INFORMATION                                         
     MT=451  DESCRIPTIVE DATA AND DICTIONARY                      
                                                                  
MF=2 MT=151  RESONANCE PARAMETERS:                                
        RESOLVED RESONANCES FOR MLBW FORMULA: 1.0E-5 EV - 200 KEV 
      PARAMETERS ARE TAKEN FROM BNL 325 4TH EDITION/1/, AND       
      SOME PARAMETERS ARE ASSUMED TO FIT THE MEASURED DATA.       
      CROSS SECTIONS CALCULATED WITH THESE PARAMETERS ARE TO      
      BE CORRECTED BY ADDING MF=3, MT=1, 2 AND 102 DATA.          
      CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGLALS  
                                                                  
                     2200-M/SEC   RES.INTEG.   REF.               
          ELASTIC      2.06 B         -         -                 
          CAPTURE      2.10 B        1.1 B     /1/                
          TOTAL        4.16 B         -         -                 
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
     BELOW 200 KEV                                                
        BACKGROUND DATA FOR MT=1 : (MT=107)-CROSS SECTIONS.       
      MT=107 (N,A)=0.04 B (10**-5 EV), 0.0043 B (2200M/S)/1/,     
             INT=5.                                               
     ABOVE 200 KEV                                                
      MT=1,2,4,51-54,91,102  TOTAL, ELASTIC, INELASTIC AND CAPTURE
         CALCULATED WITH CASTHY CODE /2/, CONSIDERING THE         
       COMPETITION WITH THE THRESHOLD REACTION CHANNELS.          
       OPTICAL POTENTIAL PARAMETERS OF C.Y.FU/3/ ARE USED.        
       THE SPHERICAL OPTICAL POTENTIAL PARAMETERS:                
            V = 46.72          VSO= 5.37    (MEV)                 
            WS=  9.13          WV = 0.0     (MEV)                 
            R =RSO= 1.26       RS = 1.39    (FM)                  
            A =ASO= 0.76       B  = 0.40    (FM)                  
      MT=102  CAPTURE DATA ARE NORMALIZED TO 4.2 MB AT 200 KEV.   
         THE DISCRETE LEVEL SCHEME TAKEN FROM REF./4/:            
            NO.      ENERGY(MEV)     SPIN-PARITY                  
           (G.S)      0.0             3/2   +                     
             1        2.523           1/2   +                     
             2        2.814           7/2   -                     
             3        3.019           3/2   -                     
             4        3.598           9/2   -                     
       CONTINUUM LEVELS ASSUMED ABOVE 3.8 MEV. THE LEVEL          
       DENSITY PARAMETERS OF ASANO ET AL./5/ ARE USED.            
    ***** JENDL-3.2 ********************************************  
    THE TOTAL AND INELASTIC SCATTERING CROSS SECTIONS WERE CAL-   
    CULATED BY USING THE OMP SET DETERMINED BY T. WATANABE.       
           V = 54.36 - 0.325EN   (MEV)                            
           WS= 2.258 + 0.1698EN  (MEV)                            
           VSO=3.341             (MEV)                            
           R  =1.20  ,A  =0.658  (FM)                             
           RS =1.32  ,B  =0.602  (FM)                             
           RSO=1.10  ,ASO=0.406  (FM)                             
    THE CROSS SECTIONS OF MT=16,22,28,103,107 IN JENDL-3.1 WERE   
    CONSIDERED AS THE COMPETING PROCESS FOR THE STATISTICAL MODEL 
    CALCULATION.                                                  
    ************************************************************  
    200 KEV - 1.0 MEV                                             
      MT=107 (N,A)-CROSS SECTION = 2.6*10**-5 B (CONSTANT):       
         ASSUMED FROM THE CALCULATED VALUE AT 1.0 MEV.            
    ABOVE 1.0 MEV                                                 
      MT=16,22,28,103,107  (N,2N), (N,NA), (N,NP), (N,P), (N,A)   
         BASED ON THE STATISTICAL MODEL CALCULATIONS WITH GNASH   
       CODE/6/, WITHOUT THE PRECOMPOUND REACTION CORRECTION.      
       TRANSMISSION COEFFICIENTS FOR PROTON AND ALPHA PARTICLE    
       ARE CALCULATED BY USING THE OMP OF BECCHETTI-GREENLEES     
       /7/ AND HUIZENGA-IGO/8/, RESPECTIVELY.                     
       LEVEL DENSITY PARAMETERS ARE BASED ON BUILT-IN VALUES.     
         AT THE ENERGY RANGE OF 4 - 20 MEV, (N,P) CROSS SECTION   
       WAS BASED ON THE EXPERIMENTAL DATA/9-11/.                  
      MT=251  MU-BAR                                              
         CALCULATED WITH OPTICAL MODEL (CASTHY).                  
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
     MT=2  CALCULATED WITH OPTICAL MODEL (CASTHY).                
     MT=51-54  CALCULATED WITH HAUSER-FESHBACH FORMULA (CASTHY)   
     MT=16,22,28  ISOTROPIC IN THE LABORATORY SYSTEM.             
     MT=91        ISOTROPIC DISTRIBUTIONS IN CM WERE CONVERTED    
                  TO THE DISTRIBUTIONS IN LAB.                    
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
     MT=16,22,28,91,103,107  EVAPORATION SPECTRA.                 
                                                                  
REFERENCES                                                        
 1) MUGHABGHAB, S.F. ET AL.: NEUTRON CROSS SECTION, VOL.1 (1981). 
 2) IGARASI, S.: J. NUCL. SCI. TECH., 12, 67 (1975).              
 3) FU, C.Y.: ATOM. DATA AND NUCL. DATA TABLES., 17, 127 (1976).  
 4) LEDERER, C.M. ET AL.: TABLE OF ISOTOPES. 7TH EDIT.            
 5) ASANO ET AL.: PRIVATE COMMUNICATION.                          
 6) YOUNG, P.G. AND  ARTHUR, E.D.: LA-6947 (1977).                
 7) BECCHETI, JR. AND GREENLEES, G.W.: POLARIZATION PHENOMENA     
   IN NUCLEAR REACTIONS, P.682 (1971).                            
 8) HUIZENGA, JR. AND IGO, G.J.: NUCL. PHYS., 29, 462 (1962).     
 9) BASS, R. ET AL.: NUCL. PHYS., 56, 569 (1964).                 
10) BORMANN, M. ET AL.: ZEITSCHRIFT F. NATURFORSCHUNG, SECTION A, 
   15, 200 (1960).                                                
11) ALEKSANDROV,D.V. ET AL.: ATOMNAYA ENERGIYA, 39(2), 137 (1975).