82-Pb-204

 82-PB-204 JAERI      EVAL-JUL87 M.MIZUMOTO                       
                      DIST-MAR02 REV3-SEP01            20010907   
----JENDL-3.3         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                             
     ***********************************************************  
                                                                  
01-06 JENDL-3.3                                                   
      Compiled by K.Shibata                                       
                                                                  
     *****   modified parts for JENDL-3.3   ********************  
      (1,451)      Updated.                                       
      (3,251)      Deleted.                                       
      (4,2)        Transformation matrix deleted.                 
      (4,16-91)    Deleted.                                       
      (5,16-91)    Deleted.                                       
      (6,16-91)    Taken from JENDL fusion file.                  
     ***********************************************************  
     -------------------------------------------------------------
      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=203  Total proton production                                  
  Sum of mt=28 and 103.                                           
                                                                  
 mt=207  Total alpha production                                   
  Sum of mt=22 and 107.                                           
                                                                  
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.                               
                                                                  
mf=6  Energy-angle distributions of secondary particles           
 mt=16, 17, 22, 28, 91, 203, 207                                  
   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).