16-S - 34

 16-S - 34 FUJI E.C.  EVAL-MAY87 H.NAKAMURA                       
                      DIST-MAR02 REV3-MAY01            20010517   
----JENDL-3.3         MATERIAL 1631                               
-----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:                               
      Resolved resonances for MLBW formula: 1.0e-5 eV - 480 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     2.08 b             -            -                
     capture     0.22 b          0.101  b       /1/               
     total       2.30 b             -            -                
                                                                  
 mf=3   Neutron cross sections                                    
    Below 480keV                                                  
      No background cross section.                                
    Above 480 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 0.3mb at 480 keV    
        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         2.127            2     +                  
              2         3.304            2     +                  
              3         3.914            0     +                  
              4         4.072            1     +                  
              5         4.115            2     +                  
        Continuum levels assumed above 4.5 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).