82-Pb-208

 82-PB-208 JAERI      EVAL-JUL87 M.MIZUMOTO                       
                      DIST-SEP89 REV2-JUN94                       
----JENDL-3.2         MATERIAL 8237                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-03  NEWLY EVALUATED FOR JENDL-3 BY M.MIZUMOTO (JAERI)          
87-11  REVISION IS RECOMMENDED.                                   
89-09  REVISION IS COMPLETED.                                     
       COMPILATION IS MADE BY T.NARITA AND T.FUKAHORI (JAERI)     
94-06 JENDL-3.2.                                                  
       RESONANCE PARAMETERS CORRECTED BY T.NAKAGAWA               
       DATA FOR MF=3,4,5 WERE ADOPTED 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   ********************  
      (3,4), (3,16). (3,17), (3,22), (3,51-91)                    
      (4,16-91), (5,16-91)                                        
             THESE DATA WERE TAKEN FROM JENDL FUSION FILE.        
      (2,151)  REICH-MOORE FORMULA ADOPTED, AND UPPER BOUNDARY    
             OF RESONANCE REGION WAS CHANGED FROM 0.8 TO 1 MEV    
      (3,2)                                                       
      (12,102), (15,102)                                          
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      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 RANGES: 1.0E-5 EV TO 1.0 MEV                          
  PARAMETERS WERE ADOPTED FROM HOREN+86 /5/ AND MUGHABGHAB/6/.    
  AVERAGE RADIATIVE WIDTH OF 0.18 EV WAS USED FOR THE RESONANCES  
  WHOSE VALUE WAS UNKNOWN.  EFFECTIVE SCATTERING RADIUS OF 9.69   
  FM/5/ WAS ADOPTED.  BACKGROUND CROSS SECTIONS WERE GIVEN TO     
  REPRODUCE THE LOW ENERGY TOTAL CROSS SECTION MEASURED AT KYOTO  
  UNIVERSITY/7/ AND THE TOTAL CROSS SECTION MEASURED BY HOREN ET  
  AL./5/ IN THE 100-460 KEV REGION.                               
                                                                  
       CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.     
                     2200 M/S             RES. INTEG.             
        ELASTIC        11.471 B               -                   
        CAPTURE        0.5007 MB           6.755 MB               
        TOTAL          11.472 B                                   
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
 BELOW 1 MEV                                                      
  BCKGROUND CROSS SECTIONS ARE GIVEN TO THE TOTAL AND ELASTIC     
  SCATTERING CROSS SECTIONS.                                      
                                                                  
 ABOVE 1 MEV                                                      
  CROSS SECTIONS OF JENDL-3.1 WERE OBTAINED WITH AN OPTICAL AND   
  STATISTICAL MODEL CALCULATION CODE CASTHY /8/.  THE OPTICAL     
  POTENTIAL PARAMETERS WERE OBTAINED BY FITTING AVERAGE TOTAL     
  CROSS SECTION OF NATURAL LEAD AS FOLLOWS,                       
       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) 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  
  /9/ FOR PROTON, LEMOS OMP MODIFIED BY ARTHUR AND YOUNG/10/      
  FOR ALPHA, LOHR-HAEBERLI OMP/11/ FOR DEUTERON, BECCHETTII-      
  GREENLEES OMP/12/ FOR TRITON AND HE-3, AND STANDARD LEVEL       
  DENSITY PARAMETERS OF SINCROS-II SYSTEM.                        
                                                                  
 MT=1  TOTAL                                                      
  CALCULATED WITH CASTHY /8/.                                     
                                                                  
 MT=2  ELASTIC SCATTERING                                         
  (TOTAL)-(ALL OTHER PARTIAL CROSS SECTIONS)                      
                                                                  
 MT=4,51-73,91  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 '*'.         
                                                                  
         NO.     ENERGY(MEV)    SPIN-PARITY (DIRECT PROCESS)      
         G.S.     0.0              0 +                            
          1       2.6146           3 -          *                 
          2       3.1977           5 -          *                 
          3       3.4751           4 -                            
          4       3.7087           5 -          *                 
          5       3.9198           6 -                            
          6       3.9464           4 -                            
          7       3.9610           5 -                            
          8       3.9957           5 -                            
          9       4.0370           7 -                            
         10       4.0450           5 -                            
         11       4.0505           3 -                            
         12       4.0854           2 +          *                 
         13       4.1060           3 -                            
         14       4.1253           4 -                            
         15       4.1410           2 +                            
         16       4.1590           5 -                            
         17       4.1804           5 -                            
         18       4.2054           6 -                            
         19       4.2295           2 -                            
         20       4.2300           4 -                            
         21       4.2535           3 -                            
         22       4.2624           5 -                            
         23       4.2960           5 -          *                 
  LEVELS ABOVE 4.296 MEV WERE ASSUMED TO BE CONTINUUM.  THE DIRECT
  INELASTIC SCATTERING CROSS SECTIONS WERE CALCULATED FOR THE     
  LEVELS AT 4.3237, 4.4235, 4.698, 4.973, 5.087, 5.242, 5.345,    
  5.483, 5.514, 5.542, 5.689, 5.813, 5.993, 6.688 AND 7.019 MEV,  
  AND ADDED TO MT=91.                                             
                                                                  
 MT=16, 17, 22        (N,2N), (N,3N), (N,NA)                      
  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/13/ (FACTOR = 1.2).  THE  
  DATA OF SIMAKOV ET AL. /14/ WERE ALSO TAKEN INTO CONSIDERATION. 
                                                                  
 MT=28 (N,N'P)                                                    
  CALCULATED WITH GNASH /15/ AND NORMALIZED TO 26 MB AT 20 MEV    
  BY WELCH+81 /16/.                                               
                                                                  
 MT=102 CAPTURE                                                   
  ESTIMATED FROM THE EXPERIMENTAL DATA BY CSIKAI+67 /17/, DRAKE+71
  /18/, BERGQVIST+72 /19/, DIVEN+60 /20/ AND LEIPUNSKIJ+58 /21/.  
                                                                  
 MT=103 (N,P)                                                     
  CALCULATED WITH GNASH /15/ AND NORMALIZED TO 4 MB AT 18 MEV BY  
  BASS+68 /22/.                                                   
                                                                  
 MT=107 (N,ALPHA)                                                 
  CALCULATED WITH GNASH /15/ AND NORMALIZED TO 1.6 MB AT 14.5 BY  
  COLEMAN+59 /23/.                                                
                                                                  
 MT=251 MU-BAR                                                    
  CALCULATED WITH CASTHY /8/.                                     
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
 MT=2                                                             
   CALCULATED WITH CASTHY /8/.                                    
 MT=51-73                                                         
   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 /15/.                                   
 MT=51-73                                                         
    TRANSITION PROBABILITIES ARE GIVEN.                           
 M=102                                                            
    FROM ENERGY BALANCE.                                          
                                                                  
MF=14 ANGULAR DISTRIBUTIONS OF SECONDARY GAMMA-RAYS               
 MT=16,17,22,28,51-73,91,102,103,107 : ASSUMED ISOTROPIC.         
                                                                  
MF=15 ENERGY DISTRIBUTION OF SECONDARY GAMMA-RAYS                 
 MT=16,17,22,28,91,107                                            
    CALCULATED WITH THE GNASH /15/.                               
 M=102                                                            
    CALCULATED WITH CASTHY /8/.                                   
                                                                  
                                                                  
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. C34, 420 (1986).              
 6) MUGHABGHAB S.F.: NEUTRON CROSS SECTIONS, VOL.1, PART B,       
    ACADEMIC PRESS (1984).                                        
 7) SHCHERBAKOV O. ET AL.: 1993 FALL MEETING OF THE ATOMIC ENERGY 
    SCI. JAPAN, P.139 (1993).                                     
 8) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
 9) PEREY F.G.: PHYS. REV., 131, 745 (1963).                      
10) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).              
11) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS., A232, 381 (1974).     
12) BECCHETTI F.D. JR. AND GREENLEES G.W.: "POLARIZATION          
   PHENOMENA IN NUCL. REACTIONS," UNIV. WISCONSIN PRESS, P.682    
   (1971).                                                        
13) TAKAHASHI A. ET AL.: JAERI-M 86-080, 393 (1986).              
14) SIMAKOV S.P. ET AL: WORKSHOP ON NUCL. DATA FOR FUSION REACTOR 
    TECHNOL., DEL MAR, MAR 3-6 (1993).                            
15) YOUNG P.G. AND ARTHUR E.D. : LA-6974 (1977).                  
16) WELCH P. ET AL. : BAP, 26, 708 (1981).                        
17) CSIKAI J. ET AL.: NUCL. PHYS. A95, 229 (1967).                
18) DRAKE D. ET AL.: PHYS. LETTERS B36, 557 (1971).               
19) BERGQVIST I. ET AL.: NUCL. PHYS. A191, 641 (1972).            
20) DIVEN B.C. ET AL. PHYS. REV. 120, 556 (1960).                 
21) LEIPUNSKIJ A.I. ET AL.: 58 GENEVA, 15, 50 (1958).             
22) BASS ET AL. : EANDC(E)-89,58 (1968).                          
23) COLEMAN R.F. ET AL. :PROC. ROY. SOC. (LONDON) 73 215 (1959).