91-Pa-233

 91-PA-233 KINKI U.+  EVAL-MAR87 T.OHSAWA, M.INOUE AND T.NAKAGAWA 
                      DIST-MAR02 REV2-FEB02            20020222   
----JENDL-3.3         MATERIAL 9137                               
-----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 RE-EVALUATION WAS PERFORMED FOR JENDL-3 BY T. OHSAWA,       
      M. INOUE (KYUSHU UNIVERSITY) AND T.NAKAGAWA(JAERI)          
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 NU-P (MT=456) AND NU-D (MT=455)                      
   MT=455   NUMBER OF DELAYED NEUTRONS                            
      TAKEN FROM TUTTLE'S SEMI-EMPIRICAL FORMULA /1/.  ENERGY     
      DEPENDENCE WAS IGNORED.                                     
   MT=456   NUMBER OF PROMPT NEUTRONS                             
      BASED ON THE SEMI-EMPIRICAL FORMULA BY BOIS AND FREHAUT /2/.
                                                                  
MF=2, MT=151     RESONANCE PARAMETERS                             
   RESOLVED RESONANCES FOR SLBW FORMULA: FROM 1.0E-5 TO 16.5 EV   
      PARAMETERS WERE TAKEN FROM THE RECOMMENDATION BY MUGHABGHAB 
      /3/ AND MODIFIED TO REPRODUCE THERMAL CROSS SECTIONS AND    
      RESONANCE INTEGRAL OF CAPTURE/3/.                           
   UNRESOLVED RESONANCE PARAMETERS: FROM 16.5 EV TO 40 KEV        
      AVERAGE RESONANCE PARAMETERS RECOMMENDED BY MUGHABGHAB /3/  
      WERE ADOPTED.                                               
          S0 = 0.75E-4,  S1 = 1.5E-4, D-OBS = 0.59 EV,            
          GAMMA WIDTH = 0.047 EV                                  
         (S1 WAS ADJUSTED WITH ASREP/5/ SO AS TO REPRODUCE TOTAL  
          AND CAPTURE CROSS SECTIONS AROUND 20 KEV.)              
                                                                  
   CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS     
                     2200-M/S          RES. INTEG.                
      TOTAL          53.051 B                                     
      ELASTIC        13.021                                       
      FISSION         0.0                2.1 B                    
      CAPTURE        40.031             864                       
                                                                  
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BELOW 40 KEV, THE RESONANCE PARAMETERS WERE GIVEN.  ABOVE 40    
  KEV, CROSS SECTIONS WERE EVALUATED AS FOLLOWS.                  
                                                                  
    MT=1  TOTAL CROSS SECTION                                     
       CALCULATED WITH THE COUPLED-CHANNEL(CC) MODEL CODE         
       JUPITOR-1/5/. 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./6/.              
                                                                  
    MT=17  (N,3N)                                                 
       CALCULATED WITH THE MODEL OF SEGEV ET AL./6/.              
                                                                  
    MT=18  FISSION                                                
       CALCULATED USING THE EXPERIMENTAL DATA ON THE FISSION      
       PROBABILITY/7/.                                            
                                                                  
    MT=53,66  INELASTIC SCATTERING TO THE 3RD AND 16TH EXCITED    
             LEVELS(MEMBERS OF THE GROUND STATE ROTATIONAL BAND). 
       CALCULATED WITH THE CONSISTENT COMBINATION OF CC AND       
       HAUSER-FESHBACH(HF) METHODS (CC/HF METHOD)/8/. THE CODE    
       JUPITOR-1 WAS USED FOR THE CC CALCULATIONS, AND ELIESE-3   
       /9/ FOR THE HF CALCULATIONS.                               
                                                                  
    MT=51-52,54-65,67-70,91  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   
       /10/.                                                      
                                                                  
    MT=102  CAPTURE                                               
       CALCULATED WITH THE CODE CASTHY/11/.  THE AVERAGE RADIATIVE
       WIDTH AND LEVEL SPACING USED TO NORMALIZE THE CALCULATION  
       ARE 40 MEV AND 0.79 EV, RESPECTIVELY/12/.                  
                                                                  
       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/,     
     EXCEPT THE 300.4 KEV-LEVEL, FOR WHICH 7/2- WAS ADOPTED       
     INSTEAD OF 7/2+ ACCORDING TO THE SUGGESTION OF GONZALEZ/16/. 
              NO.        ENERGY(MEV)       SPIN-PARITY            
              GS          0.0                3/2-                 
               1          0.0067             1/2-                 
               2          0.0572             7/2-                 
               3          0.0706             5/2-                 
               4          0.0865             5/2+                 
               5          0.0947             3/2+                 
               6          0.1036             7/2+                 
               7          0.1090             9/2+                 
               8          0.1634            11/2+                 
               9          0.1691             1/2+                 
              10          0.1792             9/2-                 
              11          0.2017             3/2+                 
              12          0.2123             5/2+                 
              13          0.2379             9/2+                 
              14          0.2573             5/2-                 
              15          0.2796             7/2+                 
              16          0.3004             7/2-                 
              17          0.3061             7/2+                 
              18          0.3661             9/2+                 
              19          0.4477             3/2-                 
              20          0.4546             3/2+                 
         CONTINUUM LEVELS WERE ASSUMED ABOVE 0.5 MEV. THE LEVEL   
         DENSITY PARAMETERS WERE TAKEN FROM GILBERT-CAMERON/7/.   
                                                                  
      MT=251   MU-BAR                                             
         CALCULATED FROM ANGULAR DISTRIBUTIONS.                   
                                                                  
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.                   
                                                                  
      MT=91  INELASTIC SCATTERING TO THE CONTINUUM                
         ISOTROPIC DISTRIBUTION WAS ASSUMED IN THE LABORATORY     
         SYSTEM.                                                  
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
                                                                  
      MT=16,17,91  (N,2N), (N,3N) AND CONTINUUM INELASTIC         
         EVAPORATION SPECTRA BASED ON THE LEVEL DENSITY PARAMETERS
                                                                  
      MT=18  FISSION                                              
         MAXWELL SPECTRUM (TAKEN FROM ENDF/B-V).                  
                                                                  
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) KIKUCHI, Y.: PRIVATE COMMUNICATION.                           
 5) TAMURA, T.: REV. MOD. PHYS. 37, 679 (1965).                   
 6) SEGEV, M. ET AL.: ANN. NUCL. ENERGY 7, 577 (1980).            
 7) GAVRON, A.: PHYS. REV. C13, 2374 (1978).                      
 8) OHSAWA, T. ET AL.: PROC. CONF. NUCL. DATA FOR BASIC AND       
    APPLIED SCI. 2, 1193 (1985).                                  
 9) IGARASI, S.: JAERI-1223 (1973).                               
10) GILBERT, M. AND CAMERON,A.G.W.: CAN. J. PHYS., 43, 1446(1966).
11) IGARASI, S.: J. NUCL. SCI. TECHNOL.,12, 67 (1975).            
12) HUSSEIN, Z. ET AL.: NUCL. SCI. ENG., 78, 370 (1981).          
13) HAOUAT,  G. ET AL.: IBID. 81, 419 (1982).                     
14) OHSAWA, T. ET AL.:J. NUCL. SCI. TECHNOL. 18, 408 (1980).      
15) ELLIS, Y.A.: NUCL. DATA SHEETS, 24, 289 (1978).               
16) GONZALEZ, L. ET AL.: NUCL. PHYS. A324, 126 (1979).