74-W -183

 74-W -183 KHI,NEDAC  EVAL-MAR87 T.WATANABE(KHI), T.ASAMI(NEDAC)  
                      DIST-MAR02 REV3-NOV01            20011121   
----JENDL-3.3         MATERIAL 7434                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
87-03  New evaluation was made for JENDL-3.                       
94-01  JENDL-3.2.                                                 
       Compiled by T.Nakagawa (ndc/jaeri)                         
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  ******  
     (3,2)                                                        
     (3,16,28)            revised                                 
     (3,203,207)          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            
     (12,22-107)          evaluated newly                         
     (13,3)               evaluated newly                         
     (14,3-107)           isotropic distributions                 
     (15,3-107)           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/.  
     -------------------------------------------------------------
                                                                  
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 2.2 keV.  Parameters were evaluated by
   examining both the experimental data/5,6,7/ and the recommended
   data of BNL/8/.  For unknown radiative width, an average value 
   of 55 milli-ev was assumed.  Parameters for a negative         
   resonance were selected so that the 2200 m/s cross section for 
   capture reproduced gave a recommended value of 10.2 barns/8/   
   and gave a good fit to the experimental data for total cross   
   sections around thermal energies.  The scattering radius was   
   assumed to be 7.3 fm.  Calculated 2200 m/sec cross sections and
   resonance integrals are as follows:                            
                                                                  
           2200 m/s cross section(b)     res. integral(b)         
   elastic        2.38                                            
   capture       10.11                      335.                  
   total         12.49                                            
                                                                  
mf=3  Neutron cross sections                                      
   Below 2.2 keV, zero background cross section was given and all 
   the cross-section data are reproduced from the evaluated       
   resonance parameters with MLBW formula.                        
                                                                  
   For JENDL-3.1, above 2.2 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                                                       
   Calculated with the combined program of the ecis and casthy    
   codes.  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, 51-60, 91 Inelastic scattering                             
   The data of mt=51 to 60 were calculated with the combined      
   program of casthy /9/ and ecis/10/.  These cross sections      
   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              1/2 -                          
       1    51    0.0465           3/2 -         *                
       2    52    0.0991           5/2 -         *                
       3    53    0.2070           7/2 -         *                
       4    54    0.2088           3/2 -                          
       5    55    0.2917           5/2 -                          
       6    56    0.3089           9/2 -         *                
       7    57    0.3095          11/2 +                          
       8    58    0.4121           7/2 -                          
       9    58    0.4530           7/2 -                          
      10    59    0.4870          13/2 +                          
      11    59    0.5330           1/2 +                          
      12    60    0.5500           9/2 -                          
      13    60    0.5953           9/2 -                          
      14    60    0.6228           9/2 +                          
   Levels above 0.624 MeV were assumed to be overlapping.  Data of
   levels 8-9, 10-11 and 12-14 were lumped as is indicated in the 
   above table.  The direct inelastic scattering cross section was
   calculated also for the levels at 0.904, 0.935, 1.025, 1.485,  
   1.866, 2.127, 2.505, 2.912, 3.404, 4.0, 4.5, 5.0 and 5.5 MeV,  
   and added to mt=91.                                            
                                                                  
   Finally, the data for mt=51,52,54,55,57,58 and 91 were adjusted
   to reproduce the benchmark integral data/16/.                  
                                                                  
 mt=16, 28 (n,2n), (n,np)                                         
   calculated with the scincros-ii system/2/.                     
                                                                  
 mt=17, 22, 103, 104, 107                                         
        (n,3n), (n,na), (n,p), (n,d), (n,a)                       
   Theoretical calculation was made with sincros-ii.  The         
   results were normalized to                                     
        (n,p)   0.0041 b at 14.7 MeV measured by Qaim/17/,        
   (n,d)+(n,np) 0.0013 b at 14.7 MeV measured by Qaim/17/,        
        (n,a)   0.0018 b at 14.7 MeV (systematics of Qaim/17/).   
                                                                  
 mt=102      capture                                              
   Calculated with the casthy code/9/ and normalized to 70+-9 mb  
   at 500 kev/18/.  Above 3 MeV, a straight line in log-log scale 
   was adopted assuming 1.0 mb at 14 MeV 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, 51-60: the same as JENDL-3.1)                        
 mt=2                                                             
   Calculated with the casthy code/9/.                            
 mt=51-60                                                         
   Calculated with the combined program of 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/1,19/.                          
                                                                  
mf=12  Photon production multiplicities and transition probability
         arrays                                                   
 mt=22, 51-60,102,103,107                                         
     Below 627.44 keV, given as multiplicities                    
     Calculated with the egnash code/2/ and processed by          
     the gamfil2 code/20/.                                        
     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/20/.                                            
                                                                  
mf=14  Photon angular distributions                               
 mt=3, 22, 51-60, 102, 103, 107                                   
     Assumed to be isotropic distributions                        
                                                                  
mf=15  Continuous photon energy spectra                           
 mt=3, 22, 103, 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. 1, 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) Oyama, Y. et al.: JAERI-CONF 96-005, 70(1996).                
17) Qaim,S.M. and Graca, C.: Nucl. Phys., A242, 317 (1975).       
18) Voignier J. et al.: Nucl. Sci. Eng., 93, 43 (1986).           
19) Kalbach C. : Phys. Rev. C37, 2350(1988).                      
20) Hida K.: JAERI-M 86-150 (1986) (in Japanese).