16-S - 36

 16-S - 36 FUJI E.C.  EVAL-MAY87 H.NAKAMURA                       
                      DIST-MAR02 REV3-MAY01            20010517   
----JENDL-3.3         MATERIAL 1637                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
87-05  Newly evaluated by H.Nakamura (fuji electric co. ltd.)     
94-02  JENDL-3.2                                                  
       New optical model calculation was performed by T. Watanabe 
       (khi).                                                     
       Data were compiled by K. Shibata (jaeri).                  
       *****  modified parts for JENDL-3.2 ******************     
       (3,1),(3,4),(3,51-55),(3,91),(3,251),(4,2),(4,51-55)       
               optical and statistical model calculations.        
       (3,2)   total - nonelastic                                 
       *******************************************************    
01-04  JENDL-3.3                                                  
       Gamma-ray production data were evaluated and compiled      
       by K. Shibata                                              
*****  modified parts for JENDL-3.3 ****************************  
(1,451)            Updated                                        
(3,251)            Deleted.                                       
(4,2)              Transformation matrix deleted.                 
(5,16-91)          INT=22.                                        
(12,16-107)        Added.                                         
(14,16-107)        Added.                                         
(15,16-107)        Added.                                         
****************************************************************  
                                                                  
 mf=1  General information                                        
      mt=451  Descriptive data and dictionary                     
                                                                  
 mf=2 mt=151 Resonance parameters: (not given)                    
                                                                  
 mf=3  Neutron cross sections                                     
      Below 1000 keV                                              
          Assumed cross sections, guided by those of s-32         
             (10**-5)eV (0.025)eV (1.0**4)eV (1.0**6)eV res.int.  
        mt=2    2.2 b     2.18 b    2.185 b  2.32339 b     -      
        mt=102  3.5 b     0.15 b    0.001 b  0.00015 b  0.12095 b 
        mt=1    5.7 b     2.33 b    2.186 b  2.32354 b     -      
      Above 1000 keV                                              
        mt=1,2,4,51-55,91,102                                     
           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 adjusted 
         to reproduce the following experimental data:            
             mt=1  total -                                        
             mt=2  elastic cross sections of s-32                 
             mt=4  inelastic -                                    
         The spherical optical potential parameters:              
             V = 38.0      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 0.15 mb at 1 MeV 
         based on s-32 capture cross section.                     
           The discrete level scheme taken from ref./4/:          
             no.     energy (MeV)     spin-parity                 
           (g.s.)      0.0              0   +                     
              1        3.291            2   +                     
              2        3.346            0   +                     
              3        4.192            3   -                     
              4        4.523            1   +                     
              5        4.575            2   +                     
         Continuum levels assumed above 5.0 MeV. The level        
         density parameters of Asano et al./5/ are used.          
     *****  JENDL-3.2 ****************************************    
     mt=1,4,51-55,91,251                                          
       Optical and statistical model calculation                  
       was performed by using the omp set given as follows:       
              V  = 58.83 - 0.5635En     (MeV)                     
              Ws = 3.609 + 0.1819En     (MeV)                     
              Vso= 4.199                (MeV)                     
              r  = 1.306,  a  = 0.452    (fm)                     
              rs = 1.124,  b  = 0.690    (fm)                     
              rso= 1.010,  aso= 0.750    (fm).                    
     *********************************************************    
        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 /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. 
                                                                  
 mf=4  Angular distributions of secondary neutrons                
      mt=2  Calculated with optical model (casthy).               
      mt=51-55  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.                
                                                                  
 mf=12 Photon production multiplicities                           
     mt=16,22,28,103,107                                          
       Multiplicities were calculated by using the egnash code    
       /9/.                                                       
     mt=102                                                       
       Multiplicities were calculated by using the casthy code    
       /2/.                                                       
     mt=51-55                                                     
       Transition probability arrays were given.                  
                                                                  
 mf=14 Photon angular distributions                               
     mt=16,22,28,51-55,91,102,103,107                             
       Isotropic                                                  
                                                                  
 mf=15 Continuous photon energy spectra                           
     mt=16,22,28,103,107                                          
       Multiplicities were calculated by using the egnash code    
       /9/.                                                       
     mt=102                                                       
       Multiplicities were calculated by using the casthy code    
       /2/.                                                       
                                                                  
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) Becchetti, 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) Yamamuro, N.: JAERI-M 90-006 (1990).