20-Ca- 40

 20-CA- 40 DEC        EVAL-MAR87 M.HATCHYA(DATA ENG. CO.)         
                      DIST-MAR02 REV3-MAY01            20010521   
----JENDL-3.3         MATERIAL 2025                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
87-03 New evaluation was made to give a full revision for JENDL-2 
      data.                                                       
87-03 compiled by T.Asami(nedac)                                  
94-04 JENDL-3.2.                                                  
       Gamma prodction data modified by T.Asami (data eng.)       
       other data were mainly adopted from JENDL fusion file.     
      Compiled by T.Nakagawa                                      
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      all cross sections except (3,103), (3,107) and (3,111)      
      all angular distributions except (4,2).                     
      all energy distributions.                                   
      (12,4), (12,102), (12,103), (12,107)                        
      (13,3)                                                      
      (15,102)                                                    
     ***********************************************************  
     -------------------------------------------------------------
      JENDL fusion file /1/  (as of Nov. 1993)                    
            Evaluated by K.Kosako (nedac) and S.Chiba (ndc/jaeri) 
            Compiled  by K.Kosako.                                
                                                                  
      -  The total cross section was modified in the energy range 
         above 10 MeV.                                            
      -  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,na) and (n,np) reaction cross sections    
         (mt=16, 22, 28) 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.      
      -  the resonance parameters, capture, (n,p), (n,a) and      
         (n,2p) cross sections and ang.  Distributions of         
         elastically scattered neutrons were taken from JENDL-3.1.
      -  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/.  
     -------------------------------------------------------------
2001-05 JENDL-3.3                                                 
        Gamma-ray production date were evaluated and compiled by  
        K.Shibata (jaeri/ndc).                                    
        ********  modified parts for JENDL-3.3  ******************
        (1,451)           Updated.                                
        (3,203), (3,207)  Calculated.                             
        (3,251)           Deleted.                                
        (4,2)             Transformation matrix deleted.          
        (4,16-91)         Deleted.                                
        (5,16-91)         Deleted.                                
        (6,16-207)        Taken form JENDL fusion file.           
        (12,16-111)       Evaluated.                              
        (14,16-111)       Evaluated.                              
        (15,16-111)       Evaluated.                              
        **********************************************************
                                                                  
                                                                  
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 500 keV.  Parameters were taken from  
   the recommended data of BNL/5/ and the data for a negative     
   resonance were added so as to reproduce the recommended thermal
   cross sections for capture and scatterng/5/.  The scattering   
   radius was assumed to be 3.6 fermi.  Calculated 2200 m/sec     
   cross sections and resonance integrals are as follows:         
                                                                  
           2200 m/s cross section(b)     res. integral(b)         
   elastic      3.022                                             
   capture      0.408                       0.2125                
   total        3.430                                             
                                                                  
mf=3  Neutron cross sections                                      
   Below 500 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-3.2, all cross-section data except for the capture,  
   (n,p) and (n,a) cross sections were adopted from JENDL fusion  
   file.  Their calculation was made 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.                 
                                                                  
 mt=1 Total                                                       
   Optical and statistical model calculation was made with        
   casthy /10/. The optical potential parameters used are:        
       V = 49.68,                Vso = 7.12   (MeV)               
      Ws = 7.76 - 0.5*En,         Wv = 0      (MeV)               
       r = 1.17,   rs = 1.09,    rso = 1.17   (fm)                
       a = 0.6,   aso = 0.6,       b = 0.69   (fm)                
   Above 10 MeV, modified to reproduce the experimental data/11,  
   12/.                                                           
   ***** comment for JENDL-3.3 ***********************************
   Above 500 keV, the total cross section is based on             
   the measurements of Cierjacks et al./13/ and Foster, Jr.       
   -Glasgow /11/.  The contributions from other isotopes were     
   subtracted from the elemental data.                            
   ***************************************************************
                                                                  
 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 cross sections were taken from JENDL fusion file.  The     
   level scheme was based on ref./4/  Contributions of the        
   direct process were calculated for the levels marked with '*', 
   using deformation parameters compiled by Raman et al./14/ and  
   Spear/15/.                                                     
         no.     energy(MeV)    spin-parity (direct process)      
                  0.0              0 +                            
          1       3.3521           0 +                            
          2       3.7369           3 -          *                 
          3       3.9045           2 +          *                 
          4       4.4915           5 -          *                 
          5       5.2129           0 +                            
          6       5.2488           2 +                            
          7       5.2788           4 +          *                 
          8       5.6142           4 -          *                 
          9       5.6296           2 +                            
         10       5.9033           1 -                            
   Levels above 5.903 MeV were assumed to be overlapping.  The    
   direct inelastic scattering cross sections were calculated for 
   the levels at 6.026, 6.286, 6.583, 6.751, 7.114, 7.466, 7.659, 
   8.099 and 8.424 MeV, and added to mt=91.                       
                                                                  
 mt=16      (n,2n)                                                
   The calculation for JENDL fusion file was not adopted.  This   
   cross section for JENDL-3.1 was evaluated on the basis of      
   experimental data of Arnord et al./16/  The threshold energy   
   was slightly modified for JENDL-3.2.                           
                                                                  
 mt=22, 28  (n,na),(n,np)                                         
   Adopted from JENDL fusion file.  Theoretical calculation was   
   made with sincros-ii.                                          
                                                                  
 mt=102     Capture                                               
   Calculated with the casthy code/17/ and normalized to 6.7 mb   
   at 30 keV.  Above 5.38 MeV, cross sections were determined     
   on the basis of the experimental data/18,19/.                  
                                                                  
 mt=103, 107, 111   (n,p), (n,a), (n,2p)                          
   Calculated with the gnash code/20/ using the above mentioned   
   optical model parameters.  The (n,p) cross sections were       
   normalized so as to fit to the experimental data of urech at   
   5.95 MeV/21/.  The (n,a) cross sections were normalized to the 
   experimental data of Barnes/22/ at 14.1 MeV.                   
                                                                  
 mt=203, 207  Total proton and alpha production                   
   mt=203 : sum of mt=28,103 and 2*(111).                         
   mt=207 : sum of mt=22 and 107.                                 
                                                                  
mf=4  Angular distributions of secondary neutrons                 
 mt=2                                                             
    Calculated with the casthy code/10/.                          
 mt=51-60                                                         
    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, 22, 28, 91                                                
    Based on kumabe's systematics/3/.                             
 mt=203, 207                                                      
    Based on kalbach's 1988 systematics/23/.                      
                                                                  
mf=12  Photon production multiplicities                           
 mt=16, 22, 28, 51-60, 91, 103, 107, and 111                      
    Calculated with the egnash code/2/.                           
 mt=102                                                           
    Calculated with the casthy code/10/.                          
                                                                  
mf=14  Photon angular distributions                               
 mt=16, 22, 28, 51-60, 91, 102, 103, 107, and 111                 
   Assumed to be isotropic in the laboratory system.              
                                                                  
mf=15  Continuous photon energy spectra                           
 mt=16, 22, 28, 91, 103, 107, and 111                             
   Calculated with the egnash code/2/.                            
 mt=102                                                           
   Calculated with the casthy code /10/.  The data measured by    
   the Tokyo Institute of Technology group /24/ were inserted     
   between 22 and 543 keV.                                        
                                                                  
                                                                  
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) Mughaghab S.F. et al.:"Neutron Cross Sections", Vol. 1, Part  
    A (1981).                                                     
 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) Foster, D.G and Glasgow, D.W.: Phys. Rev. C3, 576 (1971).     
12) Camarda, H.S. et al.: Phys. Rev. C34, 810 (1986).             
13) Cierjacks, S. et al.: KFK-1000 (1968).                        
14) Raman, S., et al.: Atom. Data and Nucl. Data Tables 36, 1     
    (1987)                                                        
15) Spear, R.H.: Atom. Data and Nucl. Data Table, 42, 55 (1989).  
16) Arnold, D.W. : taken from EXFORr (1965).                      
17) ENSDF(Evaluated Nuclear Structure Data File)                  
18) Bergqvist, I. et al.: Nucl. Phys. A231, 29 (1974).            
19) Budnar, M. et al.: INDC(YUG)-6 (1979).                        
20) Young, P.G. and Arthur, E.D. : LA-6947 (1977).                
21) Urech, S. : Nucl. Phys. A111, 184 (1968).                     
22) Barnes, J.W. et al.: J. Inorg. Nucl. Chem. 37, 399 (1975).    
23) Kalbach C. : Phys. Rev. C37, 2350(1988).                      
24) Igashira, M: private communication (2000).