19-K - 41

 19-K - 41 FUJI E.C.  EVAL-MAY87 H.NAKAMURA                       
                      DIST-MAY10                       20090828   
----JENDL-4.0         MATERIAL 1931                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
              The data were taken from JENDL-3.3.                 
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 ****************************  
              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:                                
        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                                                  
     No backgroud is given.                                       
   Above 125 keV.                                                 
        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 
     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-Greenlees      
      /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).                              
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.                 
mf=12 Photon production multiplicities                            
       Multiplicities were calculated by using the egnash code    
       Multiplicities were calculated by using the casthy code    
       Transition probability arrays were given.                  
mf=14 Photon angular distributions                                
mf=15 Continuous photon energy spectra                            
       Multiplicities were calculated by using the egnash code    
       Multiplicities were calculated by using the casthy code    
 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) 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) Adam, A. et al.: Nucl. Phys., A180, 587 (1972).               
11) Bass, R.et al.: EANDC(E)-57U, 1 (1965).                       
12) Yamamuro, N.: JAERI-M 90-006 (1990).