19-K - 40

 19-K - 40 FUJI E.C.  EVAL-MAY87 H.NAKAMURA                       
                      DIST-MAR02 REV3-MAY01            20010517   
----JENDL-3.3         MATERIAL 1928                               
-----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),(4,51-55)                     
              new optical and statistical model cal.              
(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 30 keV                                                    
        Assumed or interpolated cross sections,guided by          
      those of k-39:                                              
                (10**-5) (2200m/s)   (5.10**2)  (3.10**4)  res.int
       mt=2       2.75b    2.75 b      2.75  b    2.75  b    -    
       mt=102  1509.0 b   30.0  b /1/  0.2   b    0.023 b  13.45 b
       mt=103   370.0 b    4.4  b /1/  0.012 b    0.012 b    -    
       mt=107     2.2 b    0.39 b /1/  0.04  b    0.015 b    -    
       mt=1    1884.0 b   37.54 b      3.016 b    2.8   b    -    
  30 keV - 1.0 MeV                                                
     mt=1,2,4,102 : Calculated with casthy code /2/.              
     mt=103 : 0.012 b, Guided by measurements of H.Weigmann/3/.   
  Above 30 keV.                                                   
     mt=1,2,4,51-91,102                                           
        Total, elastic, inelastic and capture calculation with    
      casthy code /2/, considering the competition with the       
      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             4   -                      
              1        0.0296          3   -                      
              2        0.800           2   -                      
              3        0.892           5   -                      
              4        1.644           0   +                      
              5        1.959           2   +                      
      Continuum levels assumed above 2.1 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.                                                  
    ************************************************************  
     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-Grgeenlees     
      /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    
       /10/.                                                      
     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    
       /10/.                                                      
     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) Weigmann, H.: NESTOR data.                                    
 4) Fu, C.Y.: Atom. Data and Nucl. Data Tables., 17, 127 (1976).  
 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) Becchetti, 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) Yamamuro, N.: JAERI-M 90-006 (1990).