3-Li- 7

  3-Li-  7 JAERI      EVAL-DEC84 S.CHIBA AND K.SHIBATA            
 JAERI-M 88-164       DIST-MAY10                       20090827   
----JENDL-4.0         MATERIAL  328                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
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              The data were taken from JENDL-3.3.                 
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   ===========================================================    
   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.                                 
84-12  MODIFIED BY S. CHIBA                                       
       DATA OF MT=62 AND 64(MF=3,4) WERE ADDED.  DATA OF MF=4     
       (MT=2,51,57,16) AND MF=5 (MT=16,91) WERE MODIFIED.         
       PSEUDO-LEVEL REPRESENTATION WAS ADOPTED FOR THE            
       (N,N')ALPHA-T CONTINUUM (MT=52-56,58-61,63,65-84).         
       COMMENT WAS ALSO MODIFIED.                                 
87-02  LI7(N,NT) CROSS SECTION WAS MODIFIED.                      
88-02  LI7(N,N2) CROSS SECTION AND ANG. DIST. WERE MODIFIED.      
       LI7(N,N0) WAS ALSO MODIFIED SO AS TO GIVE THE TOTAL CROSS  
       SECTION WHICH IS EQUAL TO JENDL-3PR1.  THE LI7(N,N1) ANG.  
       DIST. WAS ALSO MODIFIED.  LI7(N,NT) CROSS SECTION WAS      
       FIXED TO 87-02 VERSION BY MODIFYING THE PSEUDO-LEVEL       
       CROSS SECTIONS. COMMENT WAS ALSO MODIFIED.                 
92-11 JENDL-3.2                                                   
      COMPILED BY T.NAKAGAWA                                      
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (4,2)    NUMBER OF ELEMENTS OF TRANSFORMATION MATRIX        
     ***********************************************************  
                                                                  
                                                                  
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     
                 2200 M/S (B)         RES. INTEG. (B)             
        TOTAL     1.015                    -                      
        ELASTIC   0.97                     -                      
        CAPTURE   0.045                  0.020                    
                                                                  
  MT=1      SIG-T                                                 
        BELOW 100 KEV, SIG-T = 0.97 + SIG-CAP (BARNS).            
        ABOVE 100 KEV, BASED ON THE EXPERIMENTAL DATA /1/-/4/.    
  MT=2      SIG-EL                                                
        BELOW 100 KEV, SIG-EL = 0.97 (BARNS).                     
        ABOVE 100 KEV, SIG-EL = SIG-T - SIG-REACT.                
  MT=3      NON-ELASTIC                                           
        SUM OF MT=4, 16, 102 AND 104.                             
  MT=4      TOTAL INELASTIC                                       
        SUM OF MT=51 TO 84.                                       
  MT=16     (N,2N)                                                
        BASED ON THE EXPERIMENTAL DATA /5/,/6/.                   
  MT=51     SIG-IN    0.478 MEV                                   
        BASED ON THE (N,N'GAMMA) DATA OF MORGAN /7/.              
  MT=57     SIG-IN    4.63 MEV                                    
        BASED ON THE EXPERIMENTAL DATA /8/-/10/.                  
  MT=62     SIG-IN    6.68 MEV                                    
        BASED ON A COUPLED-CHANNEL CALCULATION NORMALIZED TO THE  
        EXPERIMENTAL DATA /13,14/. THE SYMMETRIC ROTATIONAL MODEL 
        WAS ASSUMED.  THE COUPLING SCHEME WAS                     
        3/2-(G.S.) - 1/2-(0.478) - 7/2-(4.63) - 5/2-(6.68).       
        THE POTENTIAL PARAMETERS WERE AS FOLLOWS;                 
        V= 49.6 - 0.362*EL MEV, R= 1.28 FM, A= 0.620 FM           
        WS= -13.2 + 1.88*EL MEV, RI= 1.34 FM, AI= 0.104 FM        
        VSO= 5.500 MEV, RSO=1.150 FM, ASO=0.50 FM                 
        BETA(2)= 0.952,                                           
        WHERE EL MEANS LABORATORY INCIDENT ENERGY IN MEV.         
  MT=64     SIG-IN    7.467 MEV                                   
        ASSUMED TO HAVE THE SAME EXCITATION FUNCTION AS MT=53,    
        NORMALIZED TO THE EXPERIMENTAL DATA /13,14/.              
  MT=52-56,58-61,63,65-84, (N,N')ALPHA-T CONTINUUM                
        REPRESENTED BY PSEUDO-LEVELS, BINNED IN 0.5 MEV INTERVALS.
        THE CROSS SECTION WAS OBTAINED BY SUBTRACTING THE         
        CONTRIBUTION OF MT=57,62 AND 64 FROM THE (N,N')ALPHA-T    
        CROSS SECTION (MT=205). 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.                                                    
  MT=102    CAPTURE                                               
        1/V NORMALIZED TO THE THERMAL MEASUREMENT /15/.           
  MT=104    (N,D)                                                 
        THE (N,D) CROSS SECTION WAS CALCULATED WITH DWBA.         
        NORMALIZATION WAS TAKEN SO THAT THE CALCULATED CROSS      
        SECTION MIGHT BE CONSISTENT WITH THE ACTIVATION DATA /16/.
  MT=205    (N,N')ALPHA-T                                         
        BASED ON THE EXPERIMENTAL DATA /17/-/22/.                 
  MT=251    MU-BAR                                                
        CALCULATED FROM THE DATA IN FILE4.                        
                                                                  
MF=4          ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS         
  MT=2                                                            
        BELOW 4 MEV, AN R-MATRIX CALCULATION WITH THE PARAMETERS  
        OF KNOX AND LANE/23/.                                     
        BETWEEN 4 MEV AND 14 MEV, BASED ON THE EXPERIMENTAL       
        DATA /8/,/24/.                                            
        ABOVE 15 MEV, THE COUPLED-CHANNEL CALCULATION.            
  MT=16                                                           
        BASED ON THE EXPERIMENTAL DATA /13/ AT 14.2 MEV.          
        ANGULAR DISTRIBUTIONS ARE GIVEN IN THE LABORATORY SYSTEM. 
  MT=51                                                           
        BELOW  4 MEV, THE R-MATRIX CALCULATION.                   
        4 TO 10 MEV, EVALUATION OF LISKIEN/25/ WAS ADOPTED.       
        ABOVE 10 MEV, THE COUPLED-CHANNEL CALCULATION.            
  MT=57                                                           
        BELOW 8 MEV, THE R-MATRIX CALCULATION.                    
        BETWEEN 8 MEV AND 14 MEV, BASED ON THE EXPERIMENTAL       
        DATA /10/-/12/.                                           
        ABOVE 15 MEV, THE COUPLED-CHANNEL CALCULATION.            
  MT=62                                                           
        AT THE THRESHOLD, AN ISOTROPIC DISTRIBUTION WAS ASSUMED.  
        ABOVE 10 MEV, THE COUPLED-CHANNEL CALCULATION.            
  MT=64                                                           
        ISOTROPIC DISTRIBUTIONS WERE ASSUMED IN THE CENTER-OF-MASS
        SYSTEM.                                                   
  MT=52-56,58-61,63,65-84                                         
        EXPERIMENTAL DATA/13/ WERE ADOPTED.                       
                                                                  
MF=5          ENERGY DISTRIBUTION OF SECONDARY NEUTRONS           
  MT=16                                                           
        THE EVAPORATION MODEL WAS ASSUMED, WITH THE TEMPERATURE   
        DEDUCED EXPERIMENTALLY/13/ AT 14.2 MEV. THE TEMPERATURE   
        WAS EXTRAPOLATED AS                                       
        T = 0.229*SQRT(EL) MEV,                                   
        WHERE EL MEANS LABORATORY INCIDENT ENERGY IN MEV.         
                                                                  
MF=12         PHOTON-PRODUCTION MULTIPLICITIES                    
  MT=51                                                           
        M=1.0                                                     
  MT=102                                                          
        MULTIPLICITIES WERE OBTAINED FROM REF./26/.               
                                                                  
MF=14         PHOTON ANGULAR DISTRIBUTIONS                        
  MT=51                                                           
        ISOTROPIC                                                 
  MT=102                                                          
        ASSUMED TO BE ISOTROPIC.                                  
                                                                  
REFERENCES                                                        
 1) MEADOWS J.W. AND WHALEN J.F.: NUCL. SCI. ENG. 41 (1970) 351.  
 2) FOSTER, JR. D.G. AND GLASGOW D.W.: PHYS. REV. C3 (1971) 576.  
 3) GOULDING C.A. ET AL.: USNDC-3 (1972), P.161.                  
 4) LAMAZE G.P. ET AL.: BULL. AM. PHYS. SOC. 24 (1979) 862.       
 5) MATHER D.S. AND PAIN L.F.: AWRE-O-47/69 (1969).               
 6) ASHBY V.J. ET AL.: PHYS. REV. 129 (1963) 1771.                
 7) MORGAN G.L.: ORNL/TM-6247 (1978).                             
 8) HOGUE H.H. ET AL.: NUCL. SCI. ENG. 69 (1979) 22.              
 9) BABA M. ET AL.: PROC. INT. CONF. NUCLEAR CROSS SECTIONS       
    FOR TECHNOLOGY, KNOXVILLE, 1979, (1980) P.143.                
10) LISOWSKI P.W. ET AL.: LA-8342 (1980).                         
11) SCHMIDT D. ET AL.: NUCL. SCI. ENG. 96 (1987) 159.             
12) CHIBA S. ET AL.: J. NUCL. SCI. TECHNOL. 25 (1988) 210.        
13) CHIBA S. ET AL.: J. NUCL. SCI. TECHNOL. 22 (1985) 771.        
14) TAKAHASHI A. ET AL.: PRIVATE COMMUNICATION.                   
15) JURNEY E.T.: USNDC-9 (1973), P.109.                           
16) BATTAT M.E. AND RIBE F.L.: PHYS. REV. 89 (1953) 80.           
17) SMITH D.L. ET AL.: NUCL. SCI. ENG. 78 (1981) 359.             
18) LISKIEN H. ET AL.: PROC. INT. CONF. NUCLEAR DATA FOR          
    SCIENCE AND TECHNOLOGY, ANTWERP 1982, (1983) P.349.           
19) SMITH D.L. ET AL.: ANL/NDM-87 (1984).                         
20) TAKAHASHI A. ET AL.: PROC. 13TH SYMP. FUSION TECH., VARESE,   
    ITALY (1984).                                                 
21) GOLDBERG E. ET AL.: NUCL. SCI. ENG. 91, 173 (1985).           
22) MAEKAWA H. ET AL.: JAERI-M 86-125, P.130 (1986).              
23) KNOX H.D. AND LANE R.O.: NUCL. PHYS. A359 (1981) 131.         
24) KNOX H.D. ET AL.: NUCL. SCI. ENG. 69 (1979) 223.              
25) LISKIEN H.: PRIVATE COMMUNICATION.                            
26) AJZENBERG-SELOVE F. AND LAURITSEN T.: NUCL. PHYS. A227(1974)1.