13-Al- 27

 13-AL- 27 TIT,JAERI  EVAL-MAR88 Y.HARIMA,H.KITAZAWA,T.FUKAHORI   
88MITO, 473           DIST-MAR02 REV3-JUL01            20010713   
----JENDL-3.3         MATERIAL 1325                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
88-03  Evaluation was performed for JENDL-3 by Harima, Kitazawa   
       (Tokyo Institute of Tech.) and Fukahori (jaeri).  Details  
       are given in ref./1/.                                      
88-03  Compiled by Fukahori.                                      
93-12  JENDL-3.2.                                                 
       Compiled by T.Nakagawa (ndc/jaeri)                         
                                                                  
     *****   Modified parts for JENDL-3.2   ********************  
      (3,2)                                                       
      (3,66-91)            Taken from JENDL fusion file*          
        (3,4), (3,51-70)   Cross-section curves were smoothed.    
      (4,16-28), (4,91)    Taken from JENDL fusion file           
      (5,16-91)            Taken from JENDL fusion file           
      (12,51-70), (12,102)                                        
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL fusion file /2/  (as of Sep. 1993)                    
          Evaluated by B.Yu (ciae) and S.Chiba (ndc/jaeri)        
          Compiled by B.Yu.                                       
                                                                  
          Cross sections were mainly taken from JENDL-3.1, except 
       for the (n,n') (mt=66 to 70) and (n,n') continuum (mt=91)  
       reactions which were taken from the calculation with       
       sincros-II/3/.  Angular distributions of these levels      
       were taken to be equal to that of mt=66 in JENDL-3.        
          EDXs for mt=16, 22, 28 and 91 were replaced by the      
       sincros-II calculation.  mf=6 were created by f15tob       
       program.  Kumabe's systematics/4/ was used.  The pre-      
       compound/compound ratio was taken from the sincros-II      
       calculation.                                               
          Optical-model, level density and other parameters used  
       in the sincros-II calculation are described in ref./3/.    
       Level schemes were determined on the basis of ENDSF/5/.    
     -------------------------------------------------------------
                                                                  
00-10  Re-evaluated by K. Shibata (jaeri) for JENDL-3.3           
       Compiled by K. Shibata                                     
   *****  Modified parts for JENDL-3.3 ***************************
   (1,1451)                Updated                                
   (3,1),(3,2),(3,4)       Re-calculated.                         
   (3,16)                  Yamamuro's calculations /15/           
   (3,61),(3,62),(3,63)    DWBA calculations were added.          
   (3,67),(3,70)           DWBA calculations were added.          
   (3,203),(3,207)         Calcualted.                            
   (3,251)                 Deleted.                               
   (4,2)                   Transformation matrix deleted.         
   (4,16),(4,22),(4,28)    Deleted.                               
   (4,91)                  Deleted.                               
   (5,16-91)               Deleted.                               
   (6,16-91)               Taken from JENDL fusion file.          
   ***************************************************************
                                                                  
mf=1  General information                                         
 mt=451   Descriptive data and dictionary                         
                                                                  
mf=2  Resonance parameters:                                       
 mt=151                                                           
   Resolved resonances  : 1.0e-5 eV - 0.21 MeV                    
   The resonance parameters were searched, using MLBW formula/6/. 
   An initial guess of the parameters search was taken from ref.  
   /7/.                                                           
                                                                  
    Calculated 2200-m/s cross sections and resonance integrals    
                  2200-m/sec    res. integ.                       
      elastic       1.414 b          -                            
      capture       0.231 b       0.123 b                         
      total         1.645 b          -                            
                                                                  
mf=3  Neutron cross  sections                                     
 mt=1      Total cross section                                    
   Between 0.21 and 20 MeV, the cross sections were obtained by   
   an eye-guide so as to follow the experimental data.            
 mt=2      Elastic scattering cross sections                      
   Obtained by subtracting partial cross sections from the        
   total cross sections.                                          
 mt=4,51-70,91  Inelastic scattering cross sections               
   For JENDL-3.1, cross sections up to 17-th level were calculated
   with the statistical-model code casthy /8/ and the coupled-    
   channel model code ecis /9/ or jupitor-1 /10/, taking account  
   of competitive processes for neutron, proton, alpha-particle   
   and gamma-ray emission/1/. The following levels/11/ were       
   taken into account.                                            
                                                                  
          no.   energy(MeV) spin-parity                           
          g.s.     0.0        5/2 +                               
           1.      0.8438     1/2 +                               
           2.      1.0145     3/2 +                               
           3.      2.2100     7/2 +                               
           4.      2.7340     5/2 +                               
           5.      2.9814     3/2 +                               
           6.      3.0040     9/2 +                               
           7.      3.6780     1/2 +                               
           8.      3.9560     5/2 +                               
           9.      4.0540     3/2 -                               
          10.      4.4090     5/2 +                               
          11.      4.5103    11/2 +                               
          12.      4.5800     7/2 +                               
          13.      4.8120     5/2 +                               
          14.      5.1550     3/2 -                               
          15.      5.2460     5/2 +                               
          16.      5.4199     5/2 +                               
          17.      5.4330     9/2 +                               
                                                                  
   Continuum levels were assumed above 5.6 MeV.  Level density was
   calculated, using the Gilbert-Cameron formula.  The level-     
   density parameters were obtained from a cumulative plot of     
   observed levels/1/.                                            
                                                                  
   For JENDL-3.2, cross sections for mt's from 66 to 70 and conti-
   nuum inelastic were replaced with JENDL fusion file. These mt's
   correspond to the following levels.                            
                                                                  
          16.      5.4199     5/2 +                               
          17.      5.4328     5/2 +                               
          18.      5.4384     5/2 +                               
          19.      5.4998     7/2 +                               
          20.      5.5507     3/2 +                               
   Above 5.6 MeV, cross sections were summed up as the continuum  
   inelastic (mt=91).                                             
                                                                  
   Several energy points were added to mt= 4, 51-70 in order to   
   smooth their cross section curves.                             
                                                                  
   For JENDL-3.3, the direct process was considered /16/ by DWBA  
   calculations for mt=61,62,63,67,70.                            
                                                                  
 mt=16   (n,2n) cross sections                                    
   Re-calculated by the sincros-II code /17/.                     
 mt=22   (n,na) cross sections                                    
   Calculated by the statistical model with the gnash code/1,12/. 
   optical potential for alpha-particles was determined, using    
   the dispersion theory /13/.                                    
 mt=28   (n,np) cross sections                                    
   Calculated by the statistical model with the gnash code/1,12/. 
 mt=102  capture                                                  
   Calculated with the statistical-model code casthy/8/ and the   
   direct-semidirect-model code hikari/14/.  The statistical-     
   model calculations were normalized to 0.6 mb at 0.6 MeV.       
 mt=103  (n,p) cross sections                                     
   Calculated by the statistical model with the gnash code/1,12/. 
 mt=107  (n,a) cross sections                                     
   Obtained by an eye-guide to follow observed values /15/.       
 mt=111  (n,2p) cross sections                                    
   Calculated by the statistical model with the gnash code/1,12/. 
 mt=203  proton production                                        
   Sum of mt=28 and 103.                                          
 mt=207  alpha production                                         
   Sum of mt=22 and 107.                                          
                                                                  
mf=4    Angular distributions of secondary neutrons               
 mt=2                                                             
   Calculated with the statistical-model code casthy /1,8/.       
 mt=51-66                                                         
   Incoherent sum of the statistical model and coupled-channel    
   model calculations/1/.  Calculated with casthy and ecis or     
   jupitor-1.                                                     
 mt=67-70                                                         
   Assumed to be the same as mt=66.                               
                                                                  
mf=6    Energy-angle distributions of secondary particles         
 mt=16,22,28,91,203,207                                           
   Taken from JENDL fusion file.                                  
                                                                  
mf=12   gamma-ray multiplicities (below 5.80993 MeV)              
 mt=51-70                                                         
   Multiplicities were calculated from transition probabilities.  
 mt=102                                                           
   Calculated from energy balance.                                
 mt=103,107                                                       
   Calculated by using the gnash code/1,12/.                      
                                                                  
mf=13   Gamma-ray production cross sections (above 5.80993 MeV)   
 mt=3                                                             
   Calculated by the statistical model and coupled-channel model, 
   using the gnash code /12/ and the ecis /9/ or jupitor-1 code   
   /10/.  Branching ratios for transitions between discrete levels
   were taken from ref./3/.  Gamma-ray transition strength in the 
   continuum was calculated by the brink-axel giant resonance     
   model for E1 transition and by the Weisskopf single-particle   
   model for E2 and M1 transition/1/.                             
                                                                  
mf=14   Gamma-ray angular distributions                           
 mt=3,51-70,102,103,107                                           
   Isotropic distribution was assumed.                            
                                                                  
mf=15   Gamma-ray spectra                                         
 mt=3,102,103,107                                                 
   Calculated with the gnash code/1,12/                           
                                                                  
References                                                        
 1) Kitazawa H. et al.: Proc. Int. Conf. Nuclear Data for         
    Science and Technology, Mito, 1988, p.473, (1988).            
 2) Chiba S. et al.: JAERI-M 92-027, p.35 (1992).                 
 3) Yamamuro N.: JAERI-M 90-006 (1990).                           
 4) Kumabe I. et al.: Nucl. Sci. Eng., 104, 280 (1990).           
 5) ENSDF: Evaluated Nuclear Stracture Data File.                 
 6) Nakagawa T.: JAERI-M 84-192 (1984).                           
 7) Mughabghab S.F. et al.: "Neutron Cross Sections, Vol. 1       
    Part A", Academic Press (1981).                               
 8) Igarasi S. and Fukahori T.: JAERI 1321 (1991).                
 9) Raynal J.: Computer Program ECIS79 for Coupled-Channel        
    Calculations, 1979 (unpublished).                             
10) Tamura T.: Rev. Mod. Phys., 37, 679 (1965).                   
11) Endt P.M. and Van der Leun C.: Nucl. Phys., A310, 1 (1978).   
12) Young P.G. and Arthur E.D.: LA-6947 (1977).                   
13) Kitazawa H. et al.: unpublished.                              
14) Kitazawa H.: Computer Program Hikari for Direct-Semidirect    
    Capture Calculations, 1980 (unpublished).                     
15) Vonach H.: Nuclear Data Standards for Nuclear Measurements,   
    IAEA Technical Reports Series no. 227 (1983).                 
16) Shibata K.: Private communication (2000).                     
17) Yamamuro N.: Private communication (2000).