82-Pb-206

 82-PB-206 JAERI      EVAL-JUL87 M.MIZUMOTO                       
                      DIST-SEP89 REV2-APR94                       
----JENDL-3.2         MATERIAL 8231                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-03  NEWLY EVALUATED FOR JENDL-3 BY M.MIZUMOTO (JAERI)          
87-11  REVISE IS RECOMMENDED.                                     
89-09  REVISION IS COMPLETED.                                     
       COMPILATION IS MADE BY T.NARITA AND T.FUKAHORI (JAERI)     
94-04 JENDL-3.2.                                                  
        MF2:  REICH-MOORE FORMULA ADOPTED.                        
        MF3, 4, 5:  BY ADOPTING THE DATA FROM JENDL FUSION FILE   
        MF12,15:  MODIFIED BY K.SHIBATA(JAERI)                    
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (3,4), (3,16). (3,17), (3,22), (3,28), (3,51-91)            
      (4,16-91), (5,16-91)                                        
             THESE DATA WERE TAKEN FROM JENDL FUSION FILE.        
      (2,151)  REICH-MOORE FORMULA ADOPTED                        
      (3,102)  RENORMALIZED                                       
      (3,2)                                                       
      (12,102), (15,102)  CALCULATED WITH CASTHY                  
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL FUSION FILE /1/  (AS OF OCT. 1993)                    
            EVALUATED BY K.KOSAKO (NEDAC) AND S.CHIBA (NDC/JAERI) 
            COMPILED  BY K.KOSAKO.                                
                                                                  
      DATA WERE TAKEN FROM JENDL-3.1 EXCEPT FOR THE FOLLOWING:    
      -  THE INELASTIC SCATTERING CROSS SECTIONS AND ANGULAR      
         DISTRIBUTIONS OF INELASTICALLY SCATTERED NEUTRONS (EXCEPT
         CONTINUUM INELASTIC) WERE CALCULATED WITH CASTHY2Y AND   
         DWUCKY IN SINCROS-II SYSTEM/2/ INCLUDING CONTRIBUTIONS   
         FROM DIRECT REACTIONS.                                   
      -  THE (N,2N), (N,3N), (N,NA) AND (N,NP) REACTION CROSS     
         SECTIONS (MT=16, 17, 22, 28) WERE CALCULATED BY EGNASH2  
         IN THE SINCROS-II. THE (N,2N) CROSS SECTION WAS          
         RENORMALIZED TO EXPERIMENTAL DATA.                       
      -  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE REPLACED 
         WITH THOSE CALCULATED BY EGNASH2.  THE DDX'S OF THE      
         CONTINUUM NEUTRONS WERE CALCULATED BY KUMABE'S SYSTEMA-  
         TICS /3/ USING F15TOB /1/.  THE PRECOMPOUND/COMPOUND     
         RATIO WAS CALCULATED BY THE SINCROS-II CODE SYSTEM.      
      -  OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED IN
         THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./2/.     
         LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/4/.  
     -------------------------------------------------------------
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
 MT=451  DESCRIPTIVE DATA AND DICTIONARY                          
                                                                  
MF=2  RESONANCE PARAMETERS                                        
 MT=151  RESOLVED RESONANCE PARAMETERS FOR REICH-MOORE FORMULA    
  RESONANCE RANGE: 1.0E-5 EV TO 500 KEV                           
  PARAMETERS WERE EVALUATED FROM THE DATA OF HOREN+79 /5/, AND    
  MIZUMOTO+79 /6/.  VALUES OF RADIATIVE WIDTH WERE TAKEN FROM     
  REF./7/.  EFFECTIVE SCATTERING RADIUS OF 8.042 FM AND DUMMY     
  RESONANCES AT -4 AND 8 MEV WERE ADOPTED FROM REF./5/.           
                                                                  
     CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.       
                     2200 M/S             RES. INTEG.             
      ELASTIC        10.035  B                -                   
      CAPTURE         0.0306 B             0.1108 B               
      TOTAL          10.066  B                -                   
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
 BELOW 500 KEV                                                    
  NO BACKGROUND CROSS SECTIONS ARE GIVEN.                         
                                                                  
 ABOVE 500 KEV                                                    
  CROSS SECTIONS FOR JENDL-3.1 WERE OBTAINED FROM OPTICAL AND     
  STATISTICAL MODEL CALCULATIONS.  THE OPTICAL POTENTIAL          
  PARAMETERS WERE OBTAINED BY FITTING AVERAGE TOTAL CROSS SECTION 
  OF NATURAL LEAD:                                                
       V=47.0 - 0.250*E,  WS = 2.30 + 0.41*E, VSO = 6.0 (MEV)     
       R0 = 1.25       ,  RS = 1.30         , RSO = 1.30 (FM)     
       A0 = 0.65       ,  B=0.48            , AS0 = 0.689 (FM)    
  LEVEL DENSITY PARAMETERS WERE DETERMINED USING LOW-LYING LEVEL  
  DATA AND OBSERVED NEUTRON RESONANCE SPACING.                    
                                                                  
  FOR JENDL-3.2, THE (N,2N), (N,3N), (N,NA), (N,NP) AND INELASTIC 
  SCATTERING CROSS SECTIONS WERE ADOPTED FROM JENDL FUSION FILE.  
  THEY WERE CALCULATED WITH SINCROS-II SYSTEM/2/ BY ADOPTING      
  WALTER-GUSS OMP MODIFIED BY YAMAMURO/2/ FOR NEUTRON, PEREY OMP  
  /8/ FOR PROTON, LEMOS OMP MODIFIED BY ARTHUR AND YOUNG/9/ FOR   
  ALPHA, LOHR-HAEBERLI OMP/10/ FOR DEUTERON, BECCHETTII-GREENLEES 
  OMP/11/ FOR TRITON AND HE-3, AND STANDARD LEVEL DENSITY         
  PARAMETERS OF SINCROS-II SYSTEM.                                
                                                                  
  THE DATA OF TOTAL, CAPTURE, (N,P), (N,D) AND (N,A) CROSS        
  SECTIONS ARE THE SAME AS JENDL-3.1.                             
                                                                  
 MT=1  TOTAL                                                      
  CALCULATED WITH OPTICAL AND STATISTICAL MODE CODE CASTHY /12/   
                                                                  
 MT=2  ELASTIC SCATTERING                                         
  (TOTAL)-(ALL OTHER PARTIAL CROSS SECTIONS)                      
                                                                  
 MT=4,51-65.91  INELASTIC SCATTERING                              
  THE CROSS SECTIONS WERE TAKEN FROM JENDL FUSION FILE.  THE LEVEL
  SCHEME WAS ADOPTTED FROM REF./4/  CONTRIBUTIONS OF THE DIRECT   
  PROCESS WERE CALCULATED FOR THE LEVELS MARKED WITH '*', USING   
  DEFORMATION PARAMETERS COMPILED BY RAMAN ET AL./13/ AND         
  SPEAR/14/.                                                      
         NO.     ENERGY(MEV)    SPIN-PARITY (DIRECT PROCESS)      
         G.S.     0.0              0.0 +                          
          1       0.8031           2.0 +        *                 
          2       1.1650           0.0 +                          
          3       1.3405           3.0 +        *                 
          4       1.467            2.0 +                          
          5       1.6841           4.0 +        *                 
          6       1.703            1.0 +                          
          7       1.784            2.0 +        *                 
          8       1.9977           4.0 +        *                 
          9       2.149            2.0 +                          
         10       2.2002           7.0 -        *                 
         11       2.315            0.0 +                          
         12       2.379            4.0 +                          
         13       2.3842           6.0 -                          
         14       2.3914           4.0 +                          
         15       2.424            2.0 +                          
  LEVELS ABOVE 2.424 MEV WERE ASSUMED TO BE CONTINUUM.  THE       
  DIRECT INELASTIC SCATTERING CROSS SECTIONS WERE CALCULATED FOR  
  THE LEVELS AT 2.648, 3.014, 3.774, 4.114, 4.33, 5.261, 6.103    
  AND 6.187 MEV, AND ADDED TO MT=91.                              
                                                                  
 MT=16, 17, 22, 28        (N,2N), (N,3N), (N,NA), (N,NP)          
  ADOPTED FROM JENDL FUSION FILE.  THEORETICAL CALCULATION WAS    
  MADE WITH SINCROS-II.  THE (N,2N) CROSS SECTION WAS ADJUSTED TO 
  REPRODUCE THE MEASURED ENARGY SPECTRA/15/ (FACTOR = 1.2).  THE  
  DATA OF SIMAKOV ET AL. /16/ WERE ALSO TAKEN INTO CONSIDERATION. 
                                                                  
 MT=102 CAPTURE                                                   
  CALCULATED WITH CASTHY /12/, AND NORMALIZED TO 0.0085 B AT AT 50
  KEV WHICH WAS AN AVERAGE VALUE OBTAINED FROM THE RESONANCE      
  PARAMETERS.                                                     
                                                                  
 MT=103 (N,P)                                                     
  CALCULATED WITH GNASH /17/ AND NORMALIZED TO 2.0 MB AT 14.5 MEV 
  BY BELOVICKIJ+76 18/.                                           
                                                                  
 MT=107 (N,A)                                                     
  CALCULATED WITH GNASH /17/ AND MULTIPLIED BY 5.                 
                                                                  
 MT=251 MU-BAR                                                    
  CALCULATED WITH CASTHY /12/.                                    
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2                                                             
   CALCULATED WITH CASTHY /12/.                                   
 MT=51-65                                                         
   TAKEN FROM JENDL FUSION FILE.  CALCULATED WITH THE CASTHY AND  
   DWUCKY IN THE SINCROS-II SYSTEM.                               
 MT=16, 17, 22, 28, 91                                            
   TAKEN FROM JENDL FUSION FILE.                                  
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
 MT=16, 17, 22, 28, 91                                            
   TAKEN FROM JENDL FUSION FILE.                                  
                                                                  
MF=12 GAMMA-RAY MULTIPLICITY PRODUCED BY NEUTRON REACTIONS        
 MT=16,17,22,28,91,103,107                                        
    CALCULATED WITH GNASH /17/.                                   
 MT=51-65                                                         
    TRANSITION PROBABILITIES ARE GIVEN.                           
 M=102                                                            
    CALCULATED WITH CASTHY /12/.  MULTIPLICITY OF A LINE SPECTRUM 
    AT THERMAL IS 1.0.                                            
                                                                  
MF=14 ANGULAR DISTRIBUTIONS OF SECONDARY GAMMA-RAYS               
 MT=16,17,22,28,51-65,91,102,103,107 : ASSUMED ISOTROPIC.         
                                                                  
MF=15 ENERGY DISTRIBUTION OF SECONDARY GAMMA-RAYS                 
 MT=16,17,22,28,91,107                                            
    CALCULATED WITH THE GNASH /17/.                               
 M=102                                                            
    CALCULATED WITH CASTHY /12/.  AT THERMAL, A LINE SPECTRUM OF  
    6.73835 MEV WAS ASSUMED.                                      
                                                                  
REFERENCES                                                        
 1) CHIBA, S. ET AL.: JAERI-M 92-027, P.35 (1992).                
 2) YAMAMURO, N.: JAERI-M 90-006 (1990).                          
 3) KUMABE, I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).          
 4) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.       
 5) HOREN D.J. ET AL.: PHYS. REV. C20, 478 (1979).                
 6) MIZUMOTO M. ET AL.: PHYS. REV. C19 ,335 (1979).               
 7) MUGHABGHAB S.F.: NEUTRON CROSS SECTIONS, VOL.1 PART B         
    ACADEMIC PRESS (1984).                                        
 8) PEREY F.G.: PHYS. REV., 131, 745 (1963).                      
 9) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).              
10) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS., A232, 381 (1974).     
11) BECCHETTI F.D. JR. AND GREENLEES G.W.: "POLARIZATION          
   PHENOMENA IN NUCL. REACTIONS," UNIV. WISCONSIN PRESS, P.682    
   (1971).                                                        
12) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
13) RAMAN, S., ET AL.: ATOM. DATA AND NUCL. DATA TABLES 36, 1     
    (1987)                                                        
14) SPEAR, R.H.: ATOM. DATA AND NUCL. DATA TABLE, 42, 55 (1989).  
15) TAKAHASHI A. ET AL.: JAERI-M 86-080, 393 (1986).              
16) SIMAKOV S.P. ET AL: WORKSHOP ON NUCL. DATA FOR FUSION REACTOR 
    TECHNOL., DEL MAR, MAR 3-6 (1993).                            
17) YOUNG P.G. AND ARTHUR E.D.: LA-6974 (1977).                   
18) BELOVICKIJ ET AL.: 75 KIEV, 4, 209 (1976).