74-W -186

 74-W -186 KHI,NEDAC  EVAL-MAR87 T.WATANABE(KHI), T.ASAMI(NEDAC)  
                      DIST-MAR02 REV3-NOV01            20011121   
----JENDL-3.3         MATERIAL 7443                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
87-03  New evaluation was made for JENDL-3.                       
87-03  Compiled by T.Asami.                                       
94-01  JENDL-3.2.                                                 
       Compiled by T.Nakagawa (ndc/jaeri)                         
94-02  JENDL fusion file                                          
95-10  Inelastic scattering cross sections were revised.          
96-10  ddx's of charged particles were corrected.                 
       Comments modified.                                         
00-03  Reevaluation was made by T.Asami.                          
01-11  Compiled by K.Shibata (ndc/jaeri)                          
                                                                  
     *****   modified parts for JENDL-3.3  from JENDL-3.2  *****  
      (2,151)              modified                               
      (3,2)                re-calculated                          
      (3,16)               revised                                
      (3,203,204,207)      added                                  
      (3,251)              deleted                                
      (4,2)                transformation matrix deleted          
      (4,16,17,22,28,91)   deleted                                
      (5,16,17,22,28,91)   deleted                                
      (6,16,17,22,28,91)   taken from JENDL fusion file           
      (6,203,204,207)      taken from JENDL fusion file           
      (12,22,51-62,102,107)      evaluated newly                  
      (13,3)                     evaluated newly                  
      (14,3,22,51-62,102,107)    isotropic distributions          
      (15,3,22,102,107)          evaluated newly                  
     ***********************************************************  
                                                                  
                                                                  
      The JENDL fusion file /1/ and the modification of JENDL-3.2 
      from JENDL-3.1 as follows:                                  
                                                                  
                                                                  
     -------------------------------------------------------------
      JENDL fusion file /1/  (as of Jan. 1994)                    
            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 to cotinuum      
         (mt=91) was calculated with casthy2y and dwucky in       
         sincros-ii system/2/ including contributions from direct 
         reactions.                                               
      -  The (n,2n), (n,3n), (n,na), (n,np), (n,p), (n,d) and     
         (n,a) reaction cross sections (mt=16, 17, 22, 28, 103,   
         104, 107) were calculated by egnash2 in the sincros-ii.  
      -  Energy distributions of secondary neutrons were replaced 
         by 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/.  
                                                                  
   For JENDL-3.2, all cross section data except for the total,    
   elastic scattering and capture were adopted from JENDL fusion  
   file.  The calculation was made with sincros-ii system/2/ by   
   adopting Walter-Guss omp modified by Yamamuro/2/ for neutron,  
   Perey omp /12/ for proton, Lemos omp modified by Arthur and    
   Young/13/ for alpha, Lohr-Haeberli omp/14/ for deuteron,       
   Becchettii-Greenlees omp/15/ for triton and he-3, and          
   standard level density parameters of sincros-ii system.        
     -------------------------------------------------------------
                                                                  
mf=1  General information                                         
 mt=451  Descriptive data and dictionary                          
                                                                  
mf=2  Resonance parameters                                        
 mt=151  Resolved resonance parameters                            
    Resolved parameters for MLBW formula were given in the energy 
    region from 1.0e-5 eV to 15 keV.  Parameters were evaluated in
    examining both the experimental data/5,6,7/ and the           
    recommended data of BNL/8/.  For unknown radiative width, an  
    average value of 60 milli-eV was assumed.                     
    Radius was assumed to be 7.64 fermi/8/.                       
    In JENDL-3.3 to make a good fit to resonance integrals, the   
    negative resonance were removed and the radiative width of    
    18.8 eV resonance was modified.                               
    Calculated 2200 m/sec cross sections and resonance integrals  
    are as follows:                                               
            2200 m/s cross section(b)     res. integral(b)        
    elastic      0.93                                             
    capture     39.45                       529.                  
    total       40.38                                             
                                                                  
mf=3  Neutron cross sections                                      
   Below 15 keV, zero background cross section was given and  all 
   the cross-section data are reproduced from the evaluated       
   resolved resonance parameters with MLBW formula.               
                                                                  
   For JENDL-3.1, above 15 keV, the total and partial cross       
   sections were given mainly based on the theoretical calcula-   
   tions. The total, elastic and inelastic scattering, and capture
   cross sections were calculated with the coupled-channel model  
   and the spherical optical-statistical model.  The calculations 
   were performed with a combined program of casthy/9/ and ecis   
   /10/.  The spherical optical potential parameters used are:    
         V = 48.83 - 0.0809*En,    Vso = 5.6    (MeV)             
        Ws = 6.73 - 0.0536*En,      Wv = 0      (MeV)             
         r = 1.168, rs = 1.268, rso = 1.592     (fm)              
         a = 0.617, aso = 0.664, b = 0.563      (fm)              
   The deformed potential parameters were taken from the work of  
   Delaroche/11/.                                                 
                                                                  
                                                                  
 mt=1 Total                                                       
   Below 15 keV,  reproduced from the evaluated resolved resona-  
   nce parameters.                                                
   Above 15 keV, optical and statistical model calculation was    
   made with the casthy code/9/. The above-mentioned omp was used.
   almost the same as JENDL-3.1.                                  
                                                                  
 mt=2 Elastic scattering                                          
   Obtained by subtracting the sum of the partial cross sections  
   from the total cross section.                                  
                                                                  
 mt=4, 51-62, 91 Inelastic scattering                             
   The data of mt=51 to 62 were calculated with the combined      
   program of casthy /9/ and ecis/10/.  These cross sections in   
   JENDL-3.2 are the same as JENDL-3.1 except that new calculation
   was made at additional several energy points.  The cross       
   section of mt=91 was calculated with sincros-ii for JENDL      
   fusion file.  The level scheme was based on ref./4/            
   Contributions of the direct process were calculated for the    
   levels marked with '*'.                                        
                                                                  
       no.  mt   energy(MeV)     spin-parity (direct process)     
      g.s.        0.0                 0+                          
       1    51    0.1226              2+         *                
       2    52    0.3968              4+         *                
       3    53    0.7377              2+                          
       4    54    0.8088              6+         *                
       5    55    0.8618              3+                          
       6    56    0.8820              0+                          
       7    57    0.9526              2-                          
       8    58    1.0070              2+                          
       9    59    1.0316              4+                          
      10    60    1.0452              3-                          
      11    61    1.1500              0+                          
      12    62    1.2840              2+                          
      13    62    1.2980              2+                          
      14    62    1.3220              2+                          
   Levels above 1.323 MeV were assumed to be overlapping.  Data   
   given in mt=62 are sum of cross sections of 12th - 14th levels.
   The direct inelastic scattering cross section was calculated   
   also for the levels at 1.384, 2.002, 2.588, 3.0, 3.5, 4.0, 5.0,
   5.5 and 6.0 MeV, and added to mt=91.                           
                                                                  
 mt=16  (n,2n)                                                    
   Calculated with the scincros-ii system/2/ newly.               
                                                                  
 mt=17, 22, 28, 103, 104, 107                                     
        (n,3n), (n,na), (n,np), (n,p), (n,d), (n,a)               
   Adopted from JENDL fusion file.  Theoretical calculation was   
   made with sincros-ii.  The results were normalized to          
                 1.9   b at 14.  MeV measured by Frehaut/17/,     
        (n,3n)   0.058 b at 14.76MeV measured by Frehaut/17/,     
        (n,p)   0.0014 b at 14.7 MeV measured by Qaim/16/,        
  (n,d)+(n,np) 0.00025 b at 14.7 MeV measured by Qaim/16/,        
               0.00034 b at 14.87MeV measured by Kasugai/18/,     
        (n,a)  0.00076 b at 14.87MeV measured by Kasugai/18/,     
               0.00055 b at 14.7 MeV measured by Qaim/16/.        
                                                                  
 mt=102      Capture                                              
   Below 15 keV,  reproduced from the evaluated resolved resona-  
   nce parameters.                                                
   Above 15 keV, calculated with the casthy code/9/ and normalized
   to 49+-6 mb at 500 kev/19/.  Above 3 MeV, a straight line in   
   log-log scalewas adopted assuming 1.0 mb at 14 MeV (based on   
   experimental data stored in EXFOR) for JENDL-3.2.              
                                                                  
 mt=203  Total proton production                                  
   Sum of mt=28 and 103.                                          
                                                                  
 mt=204  Total deuteron production                                
   Equal to mt=104.                                               
                                                                  
 mt=207  Total alpha production                                   
   Sum of mt=22 and 107.                                          
                                                                  
mf=4  Angular distributions of secondary neutrons                 
      (mt=2, 51-62: the same as JENDL-3.1)                        
 mt=2                                                             
   Calculated with the casthy code/9/.                            
 mt=51-62                                                         
   Calculated with the combined program of the casthy/9/ and      
   ecis/10/ codes.                                                
                                                                  
mf=6  Energy-angle distributions of secondary particles           
 mt=16, 17, 22, 28, 91                                            
   Based on Kumabe's systematics/1,3/.                            
 mt=203,204,207                                                   
   Based on Kalbach's systematics/1,20/.                          
                                                                  
mf=12  Photon production multiplicities and transition probability
         arrays                                                   
 mt=51-62,102,107                                                 
     Below 1.33018 MeV, given as multiplicities                   
     Calculated with the egnash code/2/ and processed by the      
     gamfil2 code/21/.                                            
     mt=102 was calculated with the casthy code/10/.              
                                                                  
mf=13  Photon production cross sections                           
 mt=3                                                             
     Calculated with the egnash code/2/ and processed by the      
     gamfil2 code/21/.                                            
                                                                  
mf=14  Photon angular distributions                               
 mt=3,51-62, 102, 107                                             
     Assumed to be isotropic distributions                        
                                                                  
mf=15  Continuous photon energy spectra                           
 mt=3,107                                                         
     Calculated with the egnash code/2/.                          
 mt=102                                                           
     Calculated with the casthy code/10/.                         
                                                                  
                                                                  
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) Camarda H.S. et al. : Phys. Rev. C8, 1813 (1973).             
 6) Ohkubo  M. : JAERI-M 5624 (1974).                             
 7) Macklin R.L. et al. : LA-9200-MS (1982).                      
 8) Mughabghab S.F. :"Neutron Cross Sections", Vol. 2, Part B     
   (1984).                                                        
 9) Igarasi S. and Fukahori T.: JAREI 1321 (1991).                
10) Raynal J. : IAEA-SMR-9/8 p.281 (1972).                        
11) Delaroche J.F. et al. : 1979 Knoxville Conf. 336 (1979).      
12) Perey F.G.: Phys. Rev., 131, 745 (1963).                      
13) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980).              
14) Lohr J.M. and Haeberli W.: Nucl. Phys., A232, 381 (1974).     
15) Becchetti F.D. Jr. and Greenlees G.W.: "Polarization          
    Phenomena in Nucl. Reactions," Univ. Wisconsin Press, p.682   
    (1971).                                                       
16) Qaim S.M. and Graca  C.: Nucl. Phys., A242, 317 (1975).       
17) Frehaut J. et al.: 1980 BNL symposium, BNL-NCS-51245, Vol. 1, 
    p.399 (1980).                                                 
18) Kasugai Y. et al.: JAERI-M 93-046, p.277 (1993).              
19) Voignier J. et al.: Nucl. Sci. Eng., 93, 43 (1986).           
20) Kalbach C. : Phys. Rev. C37, 2350(1988).                      
21) Hida K.: JAERI-M 86-150 (1986) (in Japanese).