19-K - 41

 19-K - 41 FUJI E.C.  EVAL-MAY87 H.NAKAMURA                       
                      DIST-SEP89 REV2-FEB94                       
----JENDL-3.2         MATERIAL 1931                               
-----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),(4,51-52)                     
              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 - 125 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 INTEGRALS  
                                                                  
                  2200-M/SEC   RES. INTEG.    REF.                
         ELASTIC     2.57 B        -           -                  
         CAPTURE     1.46 B       1.58 B      /1/                 
         TOTAL       4.03 B        -           -                  
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
   BELOW 125 KEV                                                  
     MT=251  MU-BAR= 0.0164                                       
   ABOVE 125 KEV.                                                 
     MT=1,2,4,51-,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 THE EXPERIMENTAL   
      DATA OF 15 MB AT 150 KEV /4/ .                              
        THE DISCRETE LEVEL SCHEME TAKEN FROM REF./5/:             
              NO.     ENERGY(MEV)     SPIN-PARITY                 
            (G.S.)      0.0            3/2    +                   
               1        0.9804         1/2    +                   
               2        1.294          7/2    -                   
      CONTINUUM LEVELS ASSUMED ABOVE 1.5 MEV. THE LEVEL           
      DENSITY PARAMETERS OF ASANO ET AL./6/ 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.                                                  
    ************************************************************  
     MT=16(N,2N), 22(N,N'A), 28(N,N'P), 103(N,P), 107(N,A)        
        BASED ON THE STATISTICAL MODEL CALCULATIONS WITH GNASH    
      CODE /7/, WITHOUT THE PRECOMPOUND REACTION CORRECTION .     
      TRANSMISSION COEFFICIENTS FOR PROTON AND ALPHA PARTICLE     
      ARE CALCULATED BY USING THE OMP OF BECCHETTI-GEENLEES       
      /8/ AND HUIZENGA-IGO/9/, RESPECTIVELY.                      
        LEVEL DENSITY PARAMETERS ARE BASED ON BUILT-IN VALUES.    
        (N,2N), (N,P) AND (N,A) CROSS SECTIONS WERE NORMALIZED    
      TO THE EXPERIMENTAL DATA OF ADAM+/10/ FOR (N,2N), AND OF    
      BASS+/11/ FOR (N,P) AND (N,A).                              
     MT=251  MU-BAR                                               
        CALCULATED WITH OPTICAL MODEL   (CASTHY).                 
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
     MT=2  CALCULATED WITH OPTICAL MODEL (CASTHY).                
     MT=51-52  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) STUPEGIA ET AL.: J. NUCL. ENERG., 22, 267 (1968).             
 5) LEDERER, C.M. ET AL.: TABLE OF ISOTOPES. 7TH EDIT.            
 6) ASANO ET AL.: PRIVATE COMMUNICATION.                          
 7) YOUNG, P.G. AND ARTHUR, E.D.: LA-6947 (1977).                 
 8) BECCHETI, JR. AND GREENLEES, G.W.: POLARIZATION PHENOMENA     
   IN NUCLEAR REACTIONS, P.682 (1971).                            
 9) HUIZENGA, JR. AND IGO, G.J.: NUCL. PHYS., 29, 462 (1962).     
10) ADAM, A. ET AL.: NUCL. PHYS., A180, 587 (1972).               
11) BASS, R.ET AL.: EANDC(E)-57U, 1 (1965).