3-Li- 6

  3-Li-  6 JAERI      EVAL-MAR85 S.CHIBA AND K.SHIBATA            
JAERI-M 88-164        DIST-MAY10                       20090827   
----JENDL-4.0         MATERIAL  325                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
   ===========================================================    
              The data were taken from JENDL-3.3.                 
   ===========================================================    
                                                                  
                                                                  
   ===========================================================    
   JENDL-3.2 data were automatically transformed to JENDL-3.3.    
    Interpolation of spectra: 22 (unit base interpolation)        
    (3,251) deleted, T-matrix of (4,2) deleted, and others.       
   ===========================================================    
                                                                  
HISTORY                                                           
83-12  NEWLY EVALUATED BY K.SHIBATA                               
84-07  DATA OF MF=4 (MT=16,91) AND MF=5 (MT=16,91) WERE REVISED.  
       COMMENT WAS ALSO MODIFIED.                                 
85-03  MODIFIED BY S. CHIBA                                       
       DATA OF MF=3 (MT=59,63) AND MF=4 (MT=59,63) WERE ADDED.    
       DATA OF MF=3 (MT=16), MF=4 (MT=2,16,53), MF=5 (MT=16)      
       WERE REVISED.                                              
       PSEUDO-LEVEL REPRESENTATION WAS ADOPTED FOR THE            
       (N,N')ALPHA-D CONTINUUM (MT=51,52,54-56,58,60-62,64-86).   
93-12  MODIFIED BY S. CHIBA FOR JENDL-3.2                         
       DATA OF MF=3 (MT=2,3,4,54-56,58,82) AND MF=4 (MT=16,51,52, 
       54-58,60-86) WERE ADJUSTED MAMUALLY TO REPRODUCE THE DDX   
       DATA AT 14 AND 18 MEV /1,2,3/.                             
                                                                  
****  MODIFIED PARTS FOR JENDL-3.2  ******************************
(3,2),(3,3),(3,4),(3,54-56),(3,58-82)              ABOVE 10 MEV   
(4,16),(4,51-52),(4,54-58),(4,60-86)                              
******************************************************************
                                                                  
MF=1          GENERAL INFORMATION                                 
  MT=451    DESCRIPTIVE DATA                                      
                                                                  
MF=2          RESONANCE PARAMETERS                                
  MT=151    SCATTERING RADIUS ONLY.                               
                                                                  
MF=3          CROSS SECTIONS                                      
        CALCULATED 2200M/S CROSS SECTIONS AND RES. INTEGRALS      
                   2200M/S (B)     RES. INTEG. (B)                
        TOTAL      94.11               -                          
        ELASTIC    0.735               -                          
        CAPTURE    0.039            0.017                         
        (N,T)      94.03               -                          
                                                                  
  MT=1      SIG-T                                                 
        BELOW 1 MEV BASED ON THE R-MATRIX CALCULATION.  SIG-CAP   
        WAS ADDED TO THE CALCULATED CROSS SECTION.                
        ABOVE 1 MEV, BASED ON THE EXPERIMENTAL DATA /4,5,6/.      
  MT=2      SIG-EL                                                
        BELOW 1 MEV, BASED ON THE R-MATRIX CALCULATION.           
        ABOVE 1 MEV, THE CROSS SECTION WAS OBTAINED BY SUBTRACTING
        THE REACTION CROSS SECTION FROM THE TOTAL CROSS SECTION.  
  MT=3      NON-ELASTIC                                           
        SUM OF MT=4, 16, 102, 103 AND 107.                        
  MT=4      TOTAL INELASTIC                                       
        SUM OF MT=51, 52, 53, 54 AND 91.                          
  MT=16     (N,2N)LI5                                             
        BASED ON THE EXPERIMENTAL DATA /7,8,9/.                   
  MT=53     SIG-IN    2.185 MEV                                   
        BASED ON THE EXPERIMENTAL DATA /1,2,3,6,10,11,12,13/.     
  MT=57     SIG-IN    3.562 MEV                                   
        BASED ON THE EXPERIMENTAL DATA /1,2,3,6,14/               
  MT=59     SIG-IN    4.31 MEV                                    
        BASED ON A COUPLED-CHANNEL CALCULATION. THE SYMMETRIC     
        ROTATIONAL MODEL WAS ASSUMED. THE COUPLING SCHEME WAS     
        1+(G.S.) - 3+(2.185) - 2+(4.31) - 1+(5.7).                
        THE POTENTIAL PARAMETERS WERE;                            
         V  = 45.0766 MEV,          R = 1.1875 FM, A  = 0.57335 FM
         WS = 0.4432*EL-1.1631 MEV, RI= 1.6113 FM, AI = 0.26735 FM
         VSO= 5.5 MEV,              RSO=1.15 FM,   ASO= 0.5 FM    
         BETA(2)=1.1395,                                          
        WHERE EL MEANS THE INCIDENT NEUTRON ENERGY IN THE LAB.    
        SYSTEM (MEV).                                             
        ABOVE 10 MEV, BASED ON EXPERIMENTAL DATA /1,2,3/.         
  MT=63     SIG-IN    5.7 MEV                                     
        BASED ON THE CC CALCULATION NORMALIZED TO THE EXPERIMENTAL
        DATA /9/.  ABOVE 10 MEV, BASED ON EXPERIMENTAL DATA       
        /1,2,3/.                                                  
  MT=51,52,54-56,58,60-62,64-86 (N,N')ALPHA-D CONTINUUM           
        REPRESENTED BY PSEUDO-LEVELS, BINNED IN 0.5 MEV INTERVALS.
        THE (N,N')ALPHA-D CROSS SECTION WAS BASED ON THE MEASURE- 
        MENT OF ROSEN AND STEWART /15/.  THE CONTRIBUTION FROM    
        MT=53, 59 AND 63 WAS SUBTRACTED SO THAT SIG-T MIGHT BE    
        EQUAL TO THE SUM OF PARTIAL CROSS SECTIONS. THE CROSS     
        SECTION FOR EACH LEVEL WAS CALCULATED BY THE 3-BODY PHASE-
        SPACE DISTRIBUTION WITH A CORRECTION OF THE COULOMB       
        INTERACTION IN THE FINAL STATE, ASSUMING ISOTROPIC CENTER-
        OF-MASS DISTRIBUTIONS.  ADJUSTED TO REPRODUCE THE DDX DATA
        AT 14 AND 18 MEV /1,2,3/                                  
  MT=102    CAPTURE                                               
        BELOW 100 KEV, 1/V CURVE NORMALIZED TO THE THERMAL DATA OF
        JURNEY /16/.  ABOVE 100 KEV, THE INVERSE REACTION DATA OF 
        FERDINANDE ET AL./17/ WERE ADDED.                         
  MT=103    (N,P)                                                 
        BASED ON THE EXPERIMENTAL DATA /18,19/.                   
  MT=105    (N,T)ALPHA                                            
        BELOW 1 MEV, R-MATRIX CALCULATION.                        
        ABOVE 1 MEV, BASED ON THE EXPERIMENTAL DATA /20,21/.      
  MT=251    MU-BAR                                                
        CALCULATED FROM THE DATA IN FILE4.                        
                                                                  
MF=4           ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS        
  MT=2                                                            
        BELOW 500 KEV, R-MATRIX CALCULATION.                      
        BETWEEN 500 KEV AND 14 MEV, BASED ON THE EXPERIMENTAL     
        DATA /4,10,22/.                                           
        ABOVE 15 MEV, BASED ON THE CC CALCULATION.                
  MT=16                                                           
        BASED ON THE EXPERIMENTAL DATA /1,2,3,9/.                 
        ANGULAR DISTRIBUTIONS ARE GIVEN IN THE LABORATORY SYSTEM. 
  MT=53                                                           
        BELOW 4.8 MEV, ASSUMED TO BE ISOTROPIC IN CM.             
        BETWEEN 4.8 AND 14 MEV, BASED ON THE EXPERIMENTAL DATA    
        /10,23/.                                                  
        ABOVE 15 MEV, THE CC CALCULATION.                         
  MT=57                                                           
        BASED ON EXPERIMENTAL DATA /1,2,3/.                       
  MT=59                                                           
        BASED ON THE CC CALCULATION.                              
  MT=63                                                           
        BASED ON EXPERIMENTAL DATA /1,2,3/.                       
  MT=51,52,54-56,58,60-62,64-86                                   
        ADJUSTED TO REPRODUCE THE DATA /1,2,3/.                   
                                                                  
MF=5          ENERGY DISTRIBUTION OF SECONDARY NEUTRONS           
  MT=16                                                           
        THE EVAPORATION MODEL WAS ASSUMED. THE EVAPORATION        
        TEMPERATURE OF REF./9/ WAS ADOPTED. IT WAS EXTRAPOLATED   
        AS                                                        
          T = 0.176497*SQRT(EL) MEV,                              
        WHERE EL MEANS THE INCIDENT NEUTRON ENERGY IN THE LAB.    
        SYSTEM (MEV).                                             
                                                                  
MF=12         PHOTON-PRODUCTION MULTIPLICITIES                    
  MT=57                                                           
        M=1.0                                                     
  MT=102                                                          
        BASED ON THE THERMAL MEASUREMENT OF JURNEY /15/.          
                                                                  
MF=14         PHOTON ANGULAR DISTRIBUTIONS                        
  MT=57                                                           
        ISOTROPIC                                                 
  MT=102                                                          
        ASSUMED TO BE ISOTROPIC.                                  
                                                                  
REFERENCES                                                        
 1) TAKAHASII A. ET AL., TO BE PUBLISHED.                         
 2) MATSUYAMA S. ET AL., TO BE PUBLISHED.                         
 3) CHIBA S. ET AL., PPROC OF MITO CONF, P.253(1988).             
 4) KNITTER H.-H. ET AL.: EUR-5726E (1977).                       
 5) LAMAZE G.P. ET AL.: BULL. AM. PHYS. SOC. 24 (1979) 862.       
 6) GUENTHER P. ET AL.: ANL/NDM-52 (1980).                        
 7) MATHER D.S. AND PAIN L.F.: AWRE-O-47/69 (1969).               
 8) ASHBY V.J. ET AL.: PHYS. REV. 129 (1963) 1771.                
 9) CHIBA S. ET AL.: J. NUCL. SCI. TECHNOL. 22 (1985) 771.        
10) HOGUE H.H. ET AL.: NUCL. SCI. ENG. 69 (1979) 22.              
11) LISOWSKI P.W. ET AL.: LA-8342 (1980).                         
12) FOERTSCH H. ET AL.: ZFK-443 (1981), P.13.                     
13) DRAKE D.D.: DOE/NDC-24/U (1981), P.72.                        
14) BESOTOSNYJ ET AL.: YK-19 (1975), P.77.                        
15) ROSEN L. AND STEWART L.: PHYS. REV. 126 (1962) 1150.          
16) JURNEY E.T.: USNDC-9 (1973), P.109.                           
17) FERDINANDE H. ET AL.: CAN. J. PHYS. 55 (1977) 428.            
18) PRESSER G. ET AL.: NUCL. PHYS. A131 (1969) 679.               
19) MERCHEZ F. ET AL.: NUCL. PHYS. A182 (1972) 428.               
20) BARTLE C.M.: NUCL. PHYS. A330 (1979) 1.                       
21) BARTLE C.M. ET AL.: NUCL. PHYS. A397 (1983) 21.               
22) KNOX H.D. ET AL.: NUCL. SCI. ENG. 69 (1979) 223.              
23) HOPKINS J.C. ET AL.: NUCL. PHYS. A107 (1968) 139.