19-K - 0

 19-K -  0 FUJI E.C.  EVAL-MAY87 H.NAKAMURA                       
                      DIST-SEP89 REV2-FEB94                       
----JENDL-3.2         MATERIAL 1900                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-05  NEWLY EVALUATED BY H.NAKAMURA (FUJI ELECTRIC CO. LTD.)     
87-07  COMPILED BY T.FUKAHORI (JAERI).                            
94-02  JENDL-3.2                                                  
       TOTAL CROSS SECTION WAS CALCULATED BY T. WATANABE (KHI).   
       INELASTIC SCATTERING CROSS SECTIONS WERE CALCULATED BY     
       K.SHIBATA (JAERI).                                         
       GAMMA PRODUCTION DATA WERE EVALUATED BY T. ASAMI (DE).     
       DATA WERE COMPILED BY K.SHIBATA.                           
*****  MODIFIED PARTS FOR JENDL-3.2 ****************************  
(3,1),(3,4),(3,51-91),(3,251),(4,2),(4,51-61)                     
               NEW OPTICAL AND STATISTICAL MODEL CAL.             
(3,2)          TOTAL - NONELASTIC                                 
(5,16-91)      SUBSECTIONS WERE COMBINED.                         
MF=12,13,14,15 NEWLY EVALUATED.                                   
****************************************************************  
                                                                  
 NATURAL POTASSIUM CONSTRUCTED FROM ITS ISOTOPES.                 
                                                                  
MF=1  GENERAL INFORMATION                                         
     MT=451  DESCRIPTIVE DATA AND DICTIONARY                      
                                                                  
MF=2  RESONANCE PARAMETERS                                        
     MT=151  RESOLVED RESONANCES                                  
        RESONANCE REGION : 1.0E-5 EV - 200 KEV                    
       THE MULTILEVEL BREIT-WIGNER FORMULA WAS USED. PARAMETERS   
       WERE ADOPTED FROM THE FOLLOWING SOURCES.                   
          K-39 : -4.0 - 200 KEV, R = 1.80 FM                      
          K-41 : -6.6 - 125 KEV, R = 2.00 FM                      
                                                                  
       CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.     
                       2200-M/S     RES. INTEG.                   
          ELASTIC      2.096  B         -                         
          CAPTURE      2.058  B        1.118 B                    
          TOTAL        4.159  B         -                         
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
        BELOW 200 KEV, BACKGROUND CROSS SECTIONS CONSISTED OF     
       ELASTIC, CAPTURE, (N,P) AND (N,ALPHA) CROSS SECTIONS       
       WERE GIVEN.                                                
                                                                  
     MT=1  TOTAL                                                  
        FOR ENERGIES 0.2 - 20 MEV, THE WEIGHTED SUM OF ISOTOPES   
       DATA WERE TAKEN. THE ISOTOPIC CALCULATIONS WERE PERFORMED  
       BY USING CASTHY CODE/1/.                                   
     MT=2  ELASTIC SCATTERING                                     
        GIVEN AS TOTAL MINUS OTHER CROSS SECTIONS.                
     MT=4  TOTAL INELASTIC SCATTERING                             
        SUM OF MT=51-61, 91                                       
     MT=16,22,28,103,107                                          
        THE WEIGHTED SUM OF ISOTOPES WAS ADOPTED. THE CROSS       
       SECTIONS OF ISOTOPES WERE CALCULATED USING GNASH CODE/2/.  
     MT=51-61,91  INELASTIC SCATTERING                            
        ISOTOPIC DATA WERE OBTAINED FROM THE CASTHY/1/            
       CALCULATION. ISOTOPIC LEVELS WERE SORTED WITH ENERGIES.    
                                                                  
       OPTICAL POTENTIAL PARAMETERS USED IN THE CALCULATION ARE   
       AS FOLLOWS:                                                
            V  = 46.72,    R0 = 1.26, A0 = 0.76                   
            WS =  9.13,    RS = 1.39, AS = 0.40                   
            VSO=  5.37,    RSO= 1.26, ASO= 0.76                   
              ENERGIES IN MEV UNIT, LENGTHS IN FM UNIT.           
     *****  JENDL-3.2 ***************************************     
     THE CROSS SECTIONS WERE CALCULATED 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  = 1.200   , A  = 0.658  (FM)                       
            RS = 1.320   , B  = 0.602  (FM)                       
            RSO= 1.100   , ASO= 0.406  (FM)                       
     ********************************************************     
                                                                  
     MT=102  CAPTURE                                              
        ABOVE 200 KEV, THE CASTHY/1/ CALCULATION WAS ADOPTED.     
     MT=103(N,P), 107(N,ALPHA)                                    
        ABOVE 200 KEV, BASED ON CALCULATIONS USING THE GNASH/2/   
       CODE.                                                      
     MT=251  MU-BAR                                               
        CALCULATED WITH CASTHY/1/.                                
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
     MT=2,51-61                                                   
        OPTICAL AND STATISTICAL-MODEL CALCULATIONS.               
     MT=16,22,28                                                  
        ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.         
     MT=91                                                        
        ISOTROPIC DISTRIBUTIONS IN C.M. WERE CONVERTED TO THE     
        DISTRIBUTIONS IN LAB.                                     
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
     MT=16,22,28,91                                               
        CALCULATED WITH GNASH/2/.                                 
                                                                  
MF=12 PHOTON PRODUCTION MULTIPLICITY                              
     MT=102,103,107                                               
        CALCULATED WITH SINCROS-II/3/.                            
                                                                  
MF=13 PHOTON PRODUCTION CROSS SECTION                             
     MT=3                                                         
        CALCULATED WITH SINCROS-II/3/.                            
     MT=4                                                         
        GENERATED BY TAKING ACCOUNT OF BRANCHING RATIOS.          
                                                                  
MF=14 PHTON ANGULAR DISTRIBUTION                                  
     MT=3,4,102,103,107                                           
        ASSUMED TO BE ISOTROPIC.                                  
                                                                  
MF=15 PHOTON ENERGY DISTRIBUTION                                  
     MT=3,4,103,107                                               
        CALCULATED WITH SINCROS-II/3/.                            
     MT=102                                                       
        CALCULATED WITH CASTHY/1/.                                
                                                                  
REFERENCES                                                        
 1) IGARASI, S. : J. NUCL. SCI. TECHNOL., 12, 67 (1975).          
 2) YOUNG, P.G. AND ARTHUR, E.D.: LA-6947 (1977).                 
 3) YAMAMURO, N: JAERI-M 90-006 (1990).