41-Nb- 95

 41-Nb- 95 JAEA       EVAL-NOV09 A.Ichihara, K.Shibata, S.Kunieda+
                      DIST-MAY10                       20100209   
----JENDL-4.0         MATERIAL 4131                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-11 The data above the neutron energy 25 eV were calculated     
      by the POD code/1/.                                         
09-11 Compiled by A.Ichihara.                                     
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2 Resonance parameters                                        
  MT=151 Unresolved resonance region : 25 eV - 500 keV            
    The unresolved resonance parameters were calculated using     
    the ASREP code/2/.                                            
    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           1.277E+01                                    
     Elastic         5.731E+00                                    
     n,gamma         7.003E+00           5.868E+01                
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
                                                                  
  Below 25 eV, the capture and elastic scattering cross sections  
  were assumed to be in 1/v form and constant, respectively.      
  The capture cross section at 0.0253 eV was adopted from ref./3/ 
  and the scattering cross section was calculated from R = 6.7 fm.
  Unresolved resonance parameters were given in the energy range  
  from 25 eV to 500 keV.                                          
                                                                  
  MT=  1 Total cross section                                      
    Calculated with POD code /1/.                                 
                                                                  
  MT=  2 Elastic scattering cross section                         
    Calculated as (total - sum of partial cross sections).        
                                                                  
  MT=  3 Non-elastic cross section                                
    Calculated as sum of partial cross sections.                  
                                                                  
  MT=  4,51-91 (n,n') cross section                               
    Calculated with POD code /1/.                                 
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT=102 Capture cross section                                    
    The gamma-ray strength function for s-wave resonances was     
    estimated to be 45.5 (10^-4) in the POD code/1/.              
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with POD code /1/.                                 
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with POD code /1/.                                 
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with POD code /1/.                                 
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with POD code /1/.                                 
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with POD code /1/.                                 
                                                                  
  MT=203 (n,xp) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT=204 (n,xd) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT=205 (n,xt) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
  MT=206 (n,xHe3) cross section                                   
    Calculated with POD code /1/.                                 
                                                                  
  MT=207 (n,xa) cross section                                     
    Calculated with POD code /1/.                                 
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with POD code /1/.                                 
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 17 (n,3n) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 32 (n,nd) reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 51 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 52 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 53 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 54 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 55 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 56 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 57 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 58 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 59 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 60 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 61 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 62 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 63 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 64 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 65 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 66 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/1/.         
                                                                  
  MT= 91 (n,n') reaction                                          
    Neutron spectra calculated with POD/1/.                       
                                                                  
  MT= 203 (n,xp) reaction                                         
    Proton spectra calculated with POD/1/.                        
                                                                  
  MT= 204 (n,xd) reaction                                         
    Deuteron spectra calculated with POD/1/.                      
                                                                  
  MT= 205 (n,xt) reaction                                         
    Triton spectra calculated with POD/1/.                        
                                                                  
  MT= 206 (n,xHe3) reaction                                       
    He3 spectra calculated with POD/1/.                           
                                                                  
  MT= 207 (n,xa) reaction                                         
    Alpha spectra calculated with POD/1/.                         
                                                                  
MF=12 Gamma-ray multiplicities                                    
  MT=  3 Non-elastic gamma emission                               
    Calculated with POD code /1/.                                 
                                                                  
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 /1/.                                 
                                                                  
                                                        
                                                                  
***************************************************************   
*        Nuclear Model Calculations with POD Code /1/     *       
***************************************************************   
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:                                                         
  Koning and Delaroche /4/                                        
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/           
                                                                  
3. Level scheme of Nb- 95                                         
  Nuclear discrete levels were obtained from RIPL-2/9/.           
  -------------------------                                       
   No.   Ex(MeV)     J  PI                                        
  -------------------------                                       
    0    0.00000    9/2  +                                        
    1    0.23568    1/2  -                                        
    2    0.72420    7/2  +                                        
    3    0.73000    5/2  +                                        
    4    0.75673    7/2  +                                        
    5    0.79900    3/2  -                                        
    6    1.01100    5/2  -                                        
    7    1.08800    1/2  +                                        
    8    1.21900    3/2  -                                        
    9    1.27300    5/2  -                                        
   10    1.36400    7/2  -                                        
   11    1.43000    3/2  +                                        
   12    1.51400    7/2  -                                        
   13    1.58900    3/2  -                                        
   14    1.59000    3/2  +                                        
   15    1.62300    5/2  +                                        
   16    1.64500    3/2  -                                        
  -------------------------                                       
  Levels above  1.65500 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                
  ---------------------------------------------------             
  Nb- 96  12.360  0.000  0.731 -1.875  5.488  1.537               
  Nb- 95  11.759  1.231  0.764 -0.621  6.845  1.645               
  Nb- 94  12.822  0.000  0.711 -1.426  4.810  1.405               
  Nb- 93  11.549  1.244  0.969 -1.995  9.571  2.037               
  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 - 93  11.549  1.244  0.710  0.014  5.795  2.070               
  Y - 92  11.929  0.000  0.493  0.199  1.501  2.900               
  Y - 91  11.338  1.258  0.772  0.115  5.977  2.689               
  ---------------------------------------------------             
                                                                  
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              
   8.222, 7.801, 7.640, 7.390, 7.990, 7.742, 7.612 (MeV^-1)       
   for Nb-96, Nb-95, Zr-95, Y-92, Zr-94, Zr-93, and Y-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) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 2) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
     [in Japanese].                                               
 3) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I,       
     Part A," Academic Press (1981).                              
 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).