40-Zr- 95

 40-Zr- 95 JAEA       EVAL-SEP09 A.Ichihara, K.Shibata, S.Kunieda+
                      DIST-MAY10                       20091201   
----JENDL-4.0         MATERIAL 4040                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-08 The data above the neutron energy 30 keV were calculated by 
      POD.  The JENDL-3.3 data were adopted for lower energies.   
09-09 Compiled by A.Ichihara.                                     
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2 Resonance parameters                                        
  MT=151 Unresolved resonance region : 125 eV - 500 keV           
    The unresolved resonance parameters were recalculated using   
    the ASREP code/1/.                                            
    The parameters should be used only for self-shielding         
    calculation.                                                  
                                                                  
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total           6.9481E+00                                   
     Elastic         5.7345E+00                                   
     n,gamma         1.2005E+00           7.7485E+00              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    The cross sections were taken from JENDL-3.3/2/ for neutron   
    energies below 50 keV.                                        
    The cross sections were calculated with the POD code/3/       
    for neutron energies larger than 50 keV.                      
                                                                  
  MT=  2 Elastic scattering cross section                         
    Calculated as (total - sum of partial cross sections).        
                                                                  
  MT=  3 Non-elastic cross section                                
    Sum of partial cross sections.                                
                                                                  
  MT=  4,51-91 (n,n') cross section                               
    Calculated with POD code /3/.                                 
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with POD code /3/.                                 
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with POD code /3/.                                 
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with POD code /3/.                                 
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with POD code /3/.                                 
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with POD code /3/.                                 
                                                                  
  MT=102 Capture cross section                                    
    The cross sections were taken from JENDL-3.3/2/ for neutron   
    energies below 30 keV.                                        
    The cross sections were calculated with the POD code/3/       
    for neutron energies larger than 30 keV.                      
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with POD code /3/.                                 
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with POD code /3/.                                 
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with POD code /3/.                                 
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with POD code /3/.                                 
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with POD code /3/.                                 
                                                                  
  MT=203 (n,xp) cross section                                     
    Calculated with POD code /3/.                                 
                                                                  
  MT=204 (n,xd) cross section                                     
    Calculated with POD code /3/.                                 
                                                                  
  MT=205 (n,xt) cross section                                     
    Calculated with POD code /3/.                                 
                                                                  
  MT=206 (n,xHe3) cross section                                   
    Calculated with POD code /3/.                                 
                                                                  
  MT=207 (n,xa) cross section                                     
    Calculated with POD code /3/.                                 
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    The angular distributions were calculated with the POD        
    code /3/ for neutron energies larger than 50 keV.             
    Below the energy, the JENDL-3.3/2/ evaluations were           
    adopted.                                                      
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with POD/3/.                       
                                                                  
  MT= 17 (n,3n) reaction                                          
    Neutron spectra calculated with POD/3/.                       
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with POD/3/.                       
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with POD/3/.                       
                                                                  
  MT= 32 (n,nd) reaction                                          
    Neutron spectra calculated with POD/3/.                       
                                                                  
  MT= 51 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 52 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 53 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 54 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 55 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 56 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 57 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 58 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 59 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 60 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 61 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 62 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 63 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 64 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 65 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 66 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 67 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 68 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 69 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/3/.         
                                                                  
  MT= 91 (n,n') reaction                                          
    Neutron spectra calculated with POD/3/.                       
                                                                  
  MT= 203 (n,xp) reaction                                         
    Proton spectra calculated with POD/3/.                        
                                                                  
  MT= 204 (n,xd) reaction                                         
    Deuteron spectra calculated with POD/3/.                      
                                                                  
  MT= 205 (n,xt) reaction                                         
    Triton spectra calculated with POD/3/.                        
                                                                  
  MT= 206 (n,xHe3) reaction                                       
    He3 spectra calculated with POD/3/.                           
                                                                  
  MT= 207 (n,xa) reaction                                         
    Alpha spectra calculated with POD/3/.                         
                                                                  
MF=12 Gamma-ray multiplicities                                    
  MT=  3 Non-elastic gamma emission                               
    Calculated with POD code /3/.                                 
                                                                  
MF=14 Gamma-ray angular distributions                             
  MT=  3 Non-elastic gamma emission                               
    Assumed to be isotropic.                                      
                                                                  
MF=15 Gamma-ray spectra                                           
  MT=  3 Non-elastic gamma emission                               
    Calculated with POD code /3/.                                 
                                                                  
                                                        
                                                                  
***************************************************************   
*        Nuclear Model Calculations with POD Code /3/     *       
***************************************************************   
1. Theoretical models                                             
 The POD code is based on the spherical optical model, the        
distorted-wave Born approximation (DWBA), one-component exciton   
preequilibrium model, and the Hauser-Feshbach-Moldauer statis-    
tical model.  With the preequilibrim model, semi-empirical        
pickup and knockout process can be taken into account for         
composite-particle emission.  The gamma-ray emission from the     
compound nucleus can be calculated within the framework of the    
exciton model.  The code is capable of reading in particle        
transmission coefficients calculated by separate spherical or     
coupled-channel optical model code.                               
                                                                  
2. Optical model parameters                                       
Neutrons:                                                         
  The global OMP by Koning and Delaroche /4/                      
  The v_1 parameter in the real volume potential was changed      
  to 53.0 MeV from the original value 53.70 MeV.                  
Protons:                                                          
  Koning and Delaroche /4/                                        
Deuterons:                                                        
  Lohr and Haeberli /5/                                           
Tritons:                                                          
  Becchetti and Greenlees /6/                                     
He-3:                                                             
  Becchetti and Greenlees /6/                                     
Alphas:                                                           
  Lemos /7/ potentials modified by Arthur and Young /8/           
  The radius parameters r_V = r_I = 1.44 fm were used in the      
  calculation.                                                    
                                                                  
3. Level scheme of Zr- 95                                         
  Nuclear discrete levels were obtained from RIPL-2/9/.           
  Contribution of the direct process was calculated by DWBA       
  for the levels marked with '*'.                                 
  ------------------------------------------------                
   No.   Ex(MeV)     J  PI           DWBA                         
  ------------------------------------------------                
    0    0.00000    5/2  +                                        
    1    0.02300    3/2  -                                        
    2    0.95395    1/2  +     * (l=2, beta=0.12)                 
    3    1.14000    3/2  +                                        
    4    1.32377    5/2  +                                        
    5    1.61800    7/2  +                                        
    6    1.61826    3/2  +                                        
    7    1.72167    5/2  +                                        
    8    1.78800    3/2  +                                        
    9    1.89267    3/2  +                                        
   10    1.90394    5/2  +                                        
   11    1.94025    1/2  +                                        
   12    1.95592    5/2  +                                        
   13    2.02500   11/2  -     * (l=3, beta=0.17)                 
   14    2.12000    3/2  +                                        
   15    2.25000    7/2  +                                        
   16    2.25410    1/2  +                                        
   17    2.28500    3/2  +                                        
   18    2.31700    3/2  +                                        
   19    2.37224    3/2  +                                        
  ------------------------------------------------                
  Levels above  2.38224 MeV are assumed to be continuous.         
                                                                  
4. Level density parameters                                       
 Energy-dependent parameters of Mengoni-Nakajima /10/ were used   
  ---------------------------------------------------             
  Nuclei    a*    Pair     T     E0    Ematch Elv_max             
          1/MeV   MeV     MeV    MeV    MeV    MeV                
  ---------------------------------------------------             
  Zr- 96  12.403  2.450  0.708  0.681  7.693  3.120               
  Zr- 95  11.637  1.231  0.686  0.201  5.420  2.372               
  Zr- 94  12.185  2.475  0.769  0.465  8.300  2.908               
  Zr- 93  12.414  1.244  0.757 -0.394  6.540  2.548               
  Y - 95  11.759  1.231  0.472  1.209  3.029  2.717               
  Y - 94  12.145  0.000  0.464  0.098  1.560  1.530               
  Y - 93  11.549  1.244  0.710  0.014  5.795  2.070               
  Sr- 93  12.762  1.244  0.611  0.270  4.990  1.563               
  Sr- 92  11.967  2.502  0.741  0.813  7.774  2.850               
  Sr- 91  12.543  1.258  0.625  0.591  4.649  4.249               
  ---------------------------------------------------             
                                                                  
5. Gamma-ray strength functions                                   
   M1, E2: Standard Lorentzian (SLO)                              
   E1    : Standard Lorentzian (SLO) /11/                         
           The position and width parameters in the E1            
           radiation were taken from the tabulation of            
           Dietrich and Berman/12/.                               
                                                                  
6. Preequilibrium process                                         
   Preequilibrium is on for n, p, d, t, He-3, and alpha.          
                                                                  
   The single particle state density parameters were              
   8.432, 7.640, 8.126, 7.900, 7.936, 7.612, 8.524 MeV^(-1)       
   for Zr-96, Zr-95, Y-95, Sr-92, Y-94, Y-93, and Sr-93.          
                                                                  
   Effects of the particle pickup (and knockout for alpha) were   
   estimated using the semi-empirical formulas by Kalbach/13/.    
   These components were multiplied by a factor of two and        
   added to the statistical model calculation.                    
                                                                  
   Preequilibrium capture is on (the parameters were obtained     
   from /12/).                                                    
                                                                  
References                                                        
 1) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
    [in Japanese].                                                
 2) K.Shibata et al., J. Nucl. Sci. Technol. 39, 1125 (2002).     
 3) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).      
 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).           
 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization               
     Phenomena in Nuclear Reactions," p.682, The University       
     of Wisconsin Press (1971).                                   
 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972).             
 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980).                     
 9) T.Belgya et al., IAEA-TECDOC-1506 (2006).                     
10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151         
     (1994).                                                      
11) M.Brink, Ph.D thesis, Oxford University, 1955.                
12) S.S.Dietrich, B.L.Berman, Atom. Data Nucl. Data Tables,       
     38, 199 (1988).                                              
13) C.Kalbach, Z. Phys. A283, 401 (1977).