91-Pa-231

 91-PA-231 KINKI U.+  EVAL-MAR87 T.OHSAWA, M.INOUE AND T.NAKAGAWA 
                      DIST-MAR02 REV2-FEB02            20020222   
----JENDL-3.3         MATERIAL 9131                               
-----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 NEW EVALUATION WAS PERFORMED FOR JENDL-3 BY T. OHSAWA AND   
      M. INOUE.                                                   
87-07 RESONANCE PARAMETERS WERE EVALUATED BY T.NAKAGAWA(JAERI).   
88-07 UNRESOLVED RESONANCE REGION WAS MODIFIED.                   
COMPILATION WAS MADE BY T.NAKAGAWA.                               
                                                                  
MF=1    GENERAL INFORMATION                                       
   MT=451   DESCRIPTIVE DATA AND DICTIONARY                       
   MT=452   NUMBER OF NEUTRONS PER FISSION                        
        SUM OF MT'S = 455 AND 456.                                
   MT=455   DELAYED NEUTRONS                                      
        DECAY CONSTS  WERE ASSUMED TO BE SAME AS THORIUM.         
        NU-D WAS EVALUATED ON THE BASIS OF TUTTLE'S RECOMMENDA-   
        TION/1/.                                                  
   MT=456   NUMBER OF PROMPT NEUTRONS PER FISSION                 
        BASED ON THE BOIS-FREHAUT'S SEMI-EMPIRICAL FORMULA /2/.   
                                                                  
MF=2, MT=151     RESONANCE PARAMETERS                             
   RESOLVED RESONANCES FOR SLBW FORMULA: 1.0-5 - 115 EV           
        NEUTRON AND RADIATIVE WIDTHS WERE MAINLY ADOPTED FROM     
        HUSSEIN ET AL./3/, AND FISSION WIDTH ESTIMATED FROM THE   
        DATA OF FISSION AREA MEASURED BY PLATTERD ET AL. /4/.     
        FOR THE RESONANCES WHOSE FISSION AREA WAS NOT MEASURED,   
        AN AVERAGE VALUE OF 40 MICRO-EV WAS ASSUMED.  A NEGATIVE  
        RESONANCE WAS GIVEN ON THE BASIS OF RECOMMENDATION BY     
        MUGHABGHAB /5/ TO REPRODUCE RECOMMENDED THERMAL CROSS     
        SECTIONS /5/.                                             
   UNRESOLVED RESONANCES : 115 EV - 40 KEV                        
        PARAMETERS WERE BASED ON THE AVERAGE VALUES OBTAINED FROM 
        THE RESOLVED RESONANCE PARAMETERS.  S1 WAS DETERMINED     
        FROM THE OPTICAL MODEL CALCULATION.  SCATTERING RADIUS WAS
        ADJUSTED SO AS TO REPRODUCE ELASTIC SCATTERING AT 40 KEV. 
          S0 = 0.90E-4, S1 = 1.2E-4, D-OBS = 0.47EV,              
          RADIATIVE WIDTH = 0.040 EV, R = 9.05 FM                 
        BACKGROUND CROSS SECTION WAS GIVEN TO THE CAPTURE CROSS   
        SECTION TO CONNECT SMOOTHLY TO THAT IN HIGH ENERGY REGION.
                                                                  
   CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS     
                    2200 M/S        RESONANCE INTEGRALS           
      TOTAL         210.69 B           -                          
      ELASTIC         9.954            -                          
      FISSION         0.0196          4.61 B                      
      CAPTURE       200.72            596  B                      
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
       CROSS SECTION WERE REPRESENTED WITH RESONANCE PARAMETERS   
       BELOW 40 KEV.  ABOVE THIS ENERGY, CROSS SECTIONS WERE      
       EVALUATED AS FOLLOWS.                                      
                                                                  
    MT=1  TOTAL CROSS SECTION                                     
       CALCULATED WITH THE COUPLED-CHANNEL(CC) MODEL CODE         
       JUPITOR-1/6/. THE POTENTIAL PARAMETERS USED FOR THE CC-    
       CALCULATIONS ARE GIVEN BELOW.                              
                                                                  
    MT=2  ELASTIC SCATTERING                                      
       OBTAINED BY SUBTRACTING THE SUM OF CAPTURE, INELASTIC,     
       FISSION, (N,2N) AND (N,3N) REACTION CROSS SECTIONS FROM THE
       TOTAL CROSS SECTION.                                       
                                                                  
    MT=16  (N,2N)                                                 
       CALCULATED WITH THE MODEL OF SEGEV ET AL./7/.              
                                                                  
    MT=17  (N,3N)                                                 
       CALCULATED WITH THE MODEL OF SEGEV ET AL./7/.              
                                                                  
    MT=18  FISSION                                                
       BASED ON THE EXPERIMENTAL DATA OF PLATTARD/4/ BELOW 12 MEV.
       ABOVE 12 MEV, THE EVALUATION OF MANN/9/ WAS ADOPTED AFTER  
       APPROPRIATE RENORMALIZATION.                               
                                                                  
    MT=53,63  INELASTIC SCATTERING TO THE 3RD AND 13TH EXCITED    
             LEVELS(MEMBERS OF THE GROUND STATE ROTATIONAL BAND). 
       CALCULATED WITH THE CONSISTENT COMBINATION OF CC AND       
       HAUSER-FESHBACH(HF) METHODS (CC/HF METHOD)/9/. THE CODE    
       JUPITOR-1 WAS USED FOR THE CC CALCULATIONS, AND ELIESE-3   
       /10/ FOR THE HF CALCULATIONS.                              
                                                                  
    MT=51-52,54-62,64-70,91  INELASTIC SCATTERING TO THE OTHER    
             DISCRETE AND CONTINUUM LEVELS.                       
       COMPOUND NUCLEAR COMPONENT WAS CALCULATED WITH THE CODE    
       ELIESE-3 USING THE GENERALIZED TRANSMISSION COEFFICIENTS   
       CALCULATED WITH JUPITOR-1  FOR THE ENTRANCE CHANNEL. THE   
       LEVEL DENSITY PARAMETERS WERE TAKEN FROM GILBERT-CAMERON   
       /11/.                                                      
                                                                  
    MT=102  CAPTURE                                               
       CALCULATED WITH THE CODE CASTHY/12/.  THE AVERAGE RADIATIVE
       WIDTH AND LEVEL SPACING USED TO NORMALIZE THE CALCULATION  
       ARE 40 MEV AND 0.47 EV, RESPECTIVELY/3/.                   
                                                                  
       THE PARAMETERS FOR THE CC AND SPHERICAL OPTICAL POTENTIALS 
       WERE TAKEN FROM HAOUAT ET AL./13/ AND OHSAWA ET AL./14/    
       RESPECTIVELY.                                              
                  CC                    SOM                       
          V  = 46.4-0.3*EN        V  = 41.0-0.05*EN      (MEV)    
          WS =  3.6+0.4*EN        WS =  6.4+0.15*SQRT(EN)(MEV)    
          VSO=  6.2               VSO=  7.0              (MEV)    
          R  =  1.26              R  =  1.31             (FM)     
          RS =  1.26              RS =  1.38             (FM)     
          RSO=  1.12              RSO=  1.31             (FM)     
          A  =  0.63              A  =  0.47             (FM)     
          AS =  0.52              AS =  0.52             (FM)     
          ASO=  0.47              ASO=  0.47             (FM)     
          BETA2=0.190                   ---                       
          BETA4=0.071                   ---                       
                                                                  
     THE LEVEL SCHEME WAS TAKEN FROM NUCLEAR DATA SHEETS/15/.     
              NO.        ENERGY(MEV)       SPIN-PARITY            
              GS          0.0                3/2-                 
               1          0.0093             1/2-                 
               2          0.0585             7/2-                 
               3          0.0778             5/2-                 
               4          0.0842             5/2+                 
               5          0.1013             7/2+                 
               6          0.1029             3/2+                 
               7          0.1116             9/2+                 
               8          0.1340            11/2+                 
               9          0.1693            11/2-                 
              10          0.1741             5/2-                 
              11          0.1835             5/2+                 
              12          0.189             13/2+                 
              13          0.2183             7/2-                 
              14          0.2473             7/2+                 
              15          0.2720             9/2-                 
              16          0.287              1/2+                 
              17          0.3179             3/2+                 
              18          0.3202             3/2-                 
              19          0.3400            11/2-                 
              20          0.3518             5/2-                 
         CONTINUUM LEVELS WERE ASSUMED ABOVE 0.38 MEV. THE LEVEL  
         DENSITY PARAMETERS WERE TAKEN FROM GILBERT-CAMERON/11/.  
                                                                  
      MT=251   MU-BAR                                             
         CALCULATED WITH THE OPTICAL MODEL.                       
                                                                  
MF=4  ANGULAR DISTRIBUTION OF SECONDARY NEUTRONS                  
                                                                  
      MT=2   ELASTIC SCATTERING                                   
         CALCULATED WITH THE CC/HF METHOD.                        
                                                                  
      MT=51-70  INELASTIC SCATTERING                              
         CALCULATED WITH THE CC/HF METHOD FOR THE 3RD AND 13TH    
         EXCITED LEVELS. FOR THE OTHER LEVELS, CALCULATIONS WITH  
         ELIESE-3 USING THE GENERALIZED TRANSMISSION COEFFICIENTS 
         FOR THE ENTRANCE CHANNEL WERE ADOPTED, AND ISOTROPIC     
         DISTRIBUTIONS WERE ASSUMED ABOVE 5.0 MEV BECAUSE OF ZERO 
         CROSS SECTIONS.                                          
                                                                  
      MT=91  INELASTIC SCATTERING TO THE CONTINUUM                
         ISOTROPIC DISTRIBUTIONS IN LAB. SYSTEM WAS ASSUMED.      
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
                                                                  
      MT=16,17,91  (N,2N), (N,3N) AND CONTINUUM INELASTIC         
         EVAPORATION SPECTRA.                                     
                                                                  
      MT=18  FISSION                                              
         MAXWELL SPECTRUM (TAKEN FROM ENDF/B-V).                  
                                                                  
REFERENCES                                                        
 1) TUTTLE, R.J.; INDC(NDS)-107/G (1979).                         
 2) BOIS, R. AND FREHAUT, J.: CEA-R-4791 (1976).                  
 3) HUSSEIN, A. ET AL.: NUCL. SCI. ENG., 78, 370 (1981).          
 4) PLATTARD, S. ET AL.: 79 KNOXVILLE, P.491                      
 5) MUGHABGHAB, S.F.: "NEUTRON CROSS SECTIONS", VOL. 1, PART B,   
    ACADEMIC PRESS (1984).                                        
 6) TAMURA,T.: REV. MOD. PHYS. 37, 679 (1965).                    
 7) SEGEV,M. ET AL.: ANN. NUCL. ENERGY 7, 577 (1980).             
 8) MANN, F.M.: HEDL-THE-78-100 (1979).                           
 9) OHSAWA,T., ET AL.: 85 SANTA FE, 2 1193 (1985).                
10) IGARASI, S.: JAERI-1223 (1973).                               
11) GILBERT, M. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446      
    (1966).                                                       
12) IGARASI, S.: J. NUCL. SCI. TECHNOL.,12, 67 (1975).            
13) HAOUAT, G. ET AL.: IBID. 81, 419 (1982).                      
14) OHSAWA, T. ET AL.: J. NUCL. SCI. TECHNOL. 18, 408 (1980).     
15) SCHMORAK, M.R.: NUCL. DATA SHEETS 21, 91 (1977).