82-Pb-204

 82-PB-204 JAERI      EVAL-JUL87 M.MIZUMOTO                       
                      DIST-SEP89 REV2-APR94                       
----JENDL-3.2         MATERIAL 8225                               
-----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 WAS MADE BY T. NARITA AND T.FUKAHORI (JAERI)    
94-04 JENDL-3.2.                                                  
        BY ADOPTING THE DATA FROM JENDL FUSION FILE               
        GAMMA-RAY PRODUCTION DATA MODIFIED BY K.SHIBATA(JAERI)    
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (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.        
      (12,102)  FROM ENERGY BALANCE                               
      (15,102)  SPECTRUM AT 1.0E-5 EV                             
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      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 MLBW FORMULA           
  RESONANCE RANGES: 1.0E-5 EV TO 50 KEV                           
  PARAMETERS WERE EVALUATED FROM THE DATA OF HOREN+84 /5/.        
  EFFECTIVE SCATTERING RADIUS OF 8.5 FM WAS SELECTED.             
                                                                  
       CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.     
                     2200 M/S             RES. INTEG.             
      ELASTIC        11.197 B                -                    
      CAPTURE         0.661 B              1.848 B                
      TOTAL          11.857 B                -                    
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
 BELOW 50 KEV                                                     
  BACKGROUND CROSS SECTIONS ARE GIVEN FOR THE ELASTIC SCATTERING  
  AND CAPTURE CROSS SECTIONS.                                     
                                                                  
 ABOVE 50 KEV                                                     
  CROSS SECTIONS FOR JENDL-3.1 WERE OBTAINED FROM OPTICAL AND     
  STATISTICAL MODEL CALCULATIONS.  THE OPTICAL POTENTIAL PARAME-  
  TERS 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  
  /6/ FOR PROTON, LEMOS OMP MODIFIED BY ARTHUR AND YOUNG/7/ FOR   
  ALPHA, LOHR-HAEBERLI OMP/8/ FOR DEUTERON, BECCHETTII-GREENLEES  
  OMP/9/ 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 /10/   
                                                                  
 MT=2  ELASTIC SCATTERING                                         
  (TOTAL)-(ALL OTHER PARTIAL CROSS SECTIONS)                      
                                                                  
 MT=4,51-61,91  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./11/ AND         
  SPEAR/12/.                                                      
         NO.     ENERGY(MEV)    SPIN-PARITY (DIRECT PROCESS)      
         G.S.     0.0              0.0 +                          
          1       0.8992           2.0 +        *                 
          2       1.2739           4.0 +        *                 
          3       1.3514           2.0 +        *                 
          4       1.5631           4.0 +        *                 
          5       1.5836           0.0 +                          
          6       1.6047           3.0 +                          
          7       1.665            2.0 +        *                 
          8       1.682            1.0 +                          
          9       1.73             0.0 +                          
         10       1.7619           1.0 -                          
         11       1.8173           4.0 +        *                 
  LEVELS ABOVE 1.817 MEV WERE ASSUMED TO BE CONTINUUM.            
                                                                  
 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 NORMALIZED  
  TO 2.12 B AT 13.98 MEV MEASURED BY IKEDA ET AL./13/,            
                                                                  
 MT=102 CAPTURE                                                   
  CALCULATED WITH CASTHY /10/.                                    
                                                                  
 MT=103, 107   (N,P), (N,A)                                       
  CALCULATED WITH GNASH /14/.                                     
                                                                  
 MT=251 MU-BAR                                                    
  CALCULATED WITH CASTHY /10/.                                    
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2                                                             
   CALCULATED WITH CASTHY /10/.                                   
 MT=51-61                                                         
   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=16,17,22,91                                                  
    CALCULATED WITH GNASH /14/.                                   
  MT=51-61                                                        
    TRANSITION PROBABILITIES WERE GIVEN.                          
  MT=102                                                          
    FROM ENERGY BALANCE.                                          
                                                                  
MF=14 ANGULAR DISTRIBUTIONS OF SECONDARY GAMMA-RAYS               
  MT=16,17,51-61,22,91,102: ASSUMED TO BE ISOTROPIC.              
                                                                  
MF=15 ENERGY DISTRIBUTION OF SECONDARY GAMMA-RAYS                 
  MT=16,17,91,102: CALCULATED WITH THE GNASH /14/.                
                                                                  
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. C29, 2126 (1984).              
 6) PEREY F.G.: PHYS. REV., 131, 745 (1963).                      
 7) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).              
 8) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS., A232, 381 (1974).     
 9) BECCHETTI F.D. JR. AND GREENLEES G.W.: "POLARIZATION          
   PHENOMENA IN NUCL. REACTIONS," UNIV. WISCONSIN PRESS, P.682    
   (1971).                                                        
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
11) RAMAN, S., ET AL.: ATOM. DATA AND NUCL. DATA TABLES 36, 1     
    (1987)                                                        
12) SPEAR, R.H.: ATOM. DATA AND NUCL. DATA TABLE, 42, 55 (1989).  
13) IKEDA Y. ET AL.: JAERI 1312 (1987).                           
14) YOUNG P.G. AND ARTHUR E.D.: LA-6974 (1977).