92-U -232

 92-U -232 KINKI U.+  EVAL-MAR87 T.OHSAWA AND T. NAKAGAWA         
                      DIST-MAR02 REV3-FEB02            20020222   
----JENDL-3.3         MATERIAL 9219                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
   ===========================================================    
   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                                                           
87-03 EVALUATION WAS CARRIED OUT BY T. OHSAWA (KINKI UNIVERSITY)  
      AND T. NAKAGAWA (JAERI).                                    
            T.NAKAGAWA: RESONANCE PARAMETERS                      
            T.OHSAWA  : OTHER QUANTITIES                          
      COMPILATION WAS MADE BY T.NAKAGAWA (JAERI).                 
94-03 JENDL-3.2                                                   
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (3,102)      ONLY Q-VALUE WAS MODIFIED.                     
     ***********************************************************  
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451   DESCRIPTIVE DATA AND DICTIONARY                        
  MT=452   TOTAL NUMBER OF NEUTRONS PER FISSION                   
     SUM OF NU-P AND NU-D                                         
  MT=455   NUMBER OF DELAYED NEUTRONS                             
     DETERMINED FROM TUTTLE'S SEMI-EMPIRICAL FORMULA /1/.         
  MT=456   NUMBER OF PROMPT NEUTRONS                              
     BASED ON THE SEMI-EMPIRICAL FORMULA BY BOIS AND FREHAUT /2/. 
                                                                  
MF=2, MT=151        RESONANCE PARAMETERS                          
   RESOLVED RESONANCE PARAMETERS  (FROM 1.0E-5 TO 200 EV)         
     RECOMMENDATION BY MUGHABGHAB /3/ WAS ADOPTED, AND ITS FORMULA
     WAS CHANGED FROM REICH-MOORE TO MULTILEVEL BREIT- WIGNER     
     TYPE.  BACKGROUND CROSS SECTION WAS GIVEN TO REPRODUCE       
     MEASURED FISSION CROSS SECTIONS /4,5/ AT VALLEYS OF LEVELS.  
                                                                  
   CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS     
                      2200-M/S           RES. INTEG.              
     TOTAL            162.3  B                                    
     ELASTIC           10.79 B                                    
     FISSION           76.66 B            364 B                   
     CAPTURE           74.88 B            173 B                   
              THESE VALUES ARE ALMOST THE SAME AS RECOMMENDATION  
              BY MUGHABGHAB/3/ EXCEPT CAPTURE RESONANCE INTEGRAL  
              WHICH IS RECOMMENDED AS 280+-15 BARNS.              
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
   ABOVE 200 EV                                                   
   MT=1  TOTAL                                                    
         CALCULATED WITH THE SPHERICAL OPTICAL MODEL.             
                                                                  
         THE PARAMETERS FOR THE SPHERICAL OPTICAL PARAMETERS WERE 
         AS FOLLOWS:                                              
                                                                  
           V = 40.47 - 0.06*EN      (MEV),  VSO = 8.8 (MEV)       
           WS = 6.8 + 0.04*SQRT(EN) (MEV),  WV = 0.0              
           R = 1.32  (FM), RS = 1.38 (FM), RSO = 1.22 (FM)        
           A = AS = ASO = 0.47  (FM),                             
                                                                  
         THIS SET OF PARAMETERS WAS FOUND TO GIVE GOOD AGREEMENT  
         WITH THE MEASUREMENTS OF SIMPSON ET AL./6/ IN THE ENERGY 
         REGION FROM 1 KEV TO 10 KEV.                             
   MT=2   ELASTIC SCATTERING                                      
         CALCULATED WITH THE CODE CASTHY/7/.                      
   MT=16  (N,2N)                                                  
         CALCULATED WITH THE MODEL OF SEGEV-FAHIMA/8/.            
   MT=17  (N,3N)                                                  
         CALCULATED WITH THE MODEL OF SEGEV-FAHIMA/8/.            
   MT=18   FISSION                                                
         CALCULATED  BY USING  THE FISSION PROBABILITY DATA OF    
         GAVRON ET AL./9/ AND COMPOUND FORMATION CROSS SECTIONS   
         CALCULATED WITH THE OPTICAL MODEL. BELOW 1 KEV, THE CROSS
         SECTION WAS DETERMINED ON THE BASIS OF FARRELL /5/.      
   MT=51-60,91   INELASTIC SCATTERING TO THE DISCRETE AND CON-    
         TINUOUS LEVELS                                           
         CALCULATED WITH THE CODE CASTHY/7/. THE LEVEL SCHEME WAS 
         TAKEN FROM LEDERER ET AL./10/ AND SCHMORAK/11/.          
               NO.       ENERGY(MEV)   SPIN-PARITY                
               GS         0.0             0+                      
                1         0.048           2+                      
                2         0.157           4+                      
                3         0.323           6+                      
                4         0.541           8+                      
                5         0.563           1-                      
                6         0.629           3-                      
                7         0.692           0+                      
                8         0.736           2+                      
                9         0.805          10+                      
               10         0.867           2+                      
         CONTINUUM REGION WAS ASSUMED ABOVE 1.0 MEV.  THE LEVEL   
         DENSITY PARAMETERS OF GILBERT-CAMERON/12/ WERE USED.     
   MT=102  CAPTURE                                                
         CALCULATED WITH THE CODE CASTHY/7/.                      
   MT=251  MU-BAR                                                 
         CALCULATED WITH THE CODE CASTHY/7/.                      
                                                                  
MF=4   ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                
   MT=2  ELASTIC SCATTERING                                       
         CALCULATED WITH THE CODE CASTHY/7/.                      
   MT=51-60,91 INELASTIC SCATTERING                               
         CALCULATED WITH THE CODE CASTHY/7/.                      
   MT=16,17 (N,2N), (N,3N)                                        
         ASSUMED TO BE ISOTROPIC IN THE LAB SYSTEM.               
                                                                  
MF=5   ENERGY DISTRIBUTIONS OF THE SECONDARY NEUTRONS             
   MT=16,17 91  (N,2N), (N,3N) AND CONTINUUM INELASTIC            
         EVAPORATION SPECTRA.                                     
   MT=18  FISSION                                                 
         MAXWELL SPECTRUM.  THE TEMPERATURE PARAMETERS WERE ESTI- 
         MATED FROM THE SYSTEMATICS OF HOWERTON-DOYAS/13/.        
                                                                  
REFERENCES                                                        
 1) TUTTLE,R.J.: INDC(NDS)-107/G, P.29 (1979).                    
 2) BOIS,R. AND FREHAUT,J.: CEA-R-4791 (1976).                    
 3) MUGHABGHAB,S.F.: "NEUTRON CROSS SECTIONS", VOL.1, PART B,     
    ACADEMIC PRESS (1984).                                        
 4) AUCHAMPAUGH,G.F., ET AL.: NUCL. PHYS., A112, 329 (1968).      
 5) FARRELL,J.A.: LA-4420,3 (1970). DATA = EXFOR 10055002.        
 6) SIMPSON,O.D., ET AL.: NUCL. SCI. ENG. 29, 415 (1967).         
 7) IGARASI,S. AND FUKAHORI,T.: JAERI 1321 (1991).                
 8) SEGEV,M. AND FAHIMA,Y.: ANN. NUCL. ENERGY 7, 557 (1980).      
 9) GAVRON,A. ET AL.: PHYS. REV. C13, 2374 (1976).                
10) LEDERER,C.M., ET AL.: TABLE OF ISOTOPES (1978), P.1422        
11) SCHMORAK,M.K.: NUCL. DATA SHEETS 20, NO.2 (1977).             
12) GILBERT,A. AND CAMERON,A.G.: CAN. J. PHYS. 43, 1446 (1965).   
13) HOWERTON,R.J. AND DOYAS,R.J.: NUCL. SCI. ENG. 46, 414 (1971).