39-Y - 89

 39-Y - 89 JAEA       EVAL-OCT09 A.Ichihara, K.Shibata, S.Kunieda+
                      DIST-MAY10                       20091201   
----JENDL-4.0         MATERIAL 3925                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-10 The data above the neutron energy 100 keV were calculated   
      by A.Ichihara et al./1/                                     
      Resolved resonance parameters were evaluated by T.Murata.   
09-10 Compiled by A.Ichihara.                                     
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2 Resonance parameters                                        
  MT=151 Resolved and unresolved resoannce parameters             
    Resolved resonance region (Reich-Moore formula): below 100 keV
      Based on the neutron widths measured by Agrawal et al./2/   
      and the capture widths measured by Boldeman et al./3/       
                                                                  
  MT=151 Unresolved resonance region : 100 keV - 200 keV          
    The unresolved resonance parameters were calculated using     
    the ASREP code/4/.                                            
    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           8.9394E+00                                   
     Elastic         7.6555E+00                                   
     n,gamma         1.2839E+00           8.6261E-01              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    Calculated with POD code /5/.                                 
                                                                  
  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 /5/.                                 
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with POD code /5/.                                 
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with POD code /5/.                                 
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with POD code /5/.                                 
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with POD code /5/.                                 
                                                                  
  MT=102 Capture cross section                                    
    Calculated with POD code /5/.                                 
    The strength function was normalized to obtain 10.6 mb        
    at neutron energy 100 keV /1/.                                
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with POD code /5/.                                 
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with POD code /5/.                                 
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with POD code /5/.                                 
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with POD code /5/.                                 
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with POD code /5/.                                 
                                                                  
  MT=203 (n,xp) cross section                                     
    Calculated with POD code /5/.                                 
                                                                  
  MT=204 (n,xd) cross section                                     
    Calculated with POD code /5/.                                 
                                                                  
  MT=205 (n,xt) cross section                                     
    Calculated with POD code /5/.                                 
                                                                  
  MT=206 (n,xHe3) cross section                                   
    Calculated with POD code /5/.                                 
                                                                  
  MT=207 (n,xa) cross section                                     
    Calculated with POD code /5/.                                 
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with POD code /5/.                                 
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with POD/5/.                       
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with POD/5/.                       
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with POD/5/.                       
                                                                  
  MT= 32 (n,nd) reaction                                          
    Neutron spectra calculated with POD/5/.                       
                                                                  
  MT= 51 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 52 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 53 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 54 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 55 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 56 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 57 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 58 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 59 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 60 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 61 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 62 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 63 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 64 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 65 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 66 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 67 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 68 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 69 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 70 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 71 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 72 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 73 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 74 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 75 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 76 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 77 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 78 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 79 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 80 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 81 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 82 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 83 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/5/.         
                                                                  
  MT= 91 (n,n') reaction                                          
    Neutron spectra calculated with POD/5/.                       
                                                                  
  MT= 203 (n,xp) reaction                                         
    Proton spectra calculated with POD/5/.                        
                                                                  
  MT= 204 (n,xd) reaction                                         
    Deuteron spectra calculated with POD/5/.                      
                                                                  
  MT= 205 (n,xt) reaction                                         
    Triton spectra calculated with POD/5/.                        
                                                                  
  MT= 206 (n,xHe3) reaction                                       
    He3 spectra calculated with POD/5/.                           
                                                                  
  MT= 207 (n,xa) reaction                                         
    Alpha spectra calculated with POD/5/.                         
                                                                  
MF=12 Gamma-ray multiplicities                                    
  MT=  3 Non-elastic gamma emission                               
    Calculated with POD code /5/.                                 
                                                                  
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 /5/.                                 
                                                                  
                                                        
                                                                  
***************************************************************   
*        Nuclear Model Calculations with POD Code /5/     *       
***************************************************************   
1. Theoretical models                                             
 The POD code is based on the spherical optical model, the        
distorted-wave Born approximaiton (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 /6/                                        
Protons:                                                          
  Koning and Delaroche /6/                                        
  The radius parameter r_V = 1.25 fm was used in the calculation. 
Deuterons:                                                        
  Lohr and Haeberli /7/                                           
Tritons:                                                          
  Becchetti and Greenlees /8/                                     
He-3:                                                             
  Becchetti and Greenlees /8/                                     
Alphas:                                                           
  Lemos /9/ potentials modified by Arthur and Young /10/.         
  The radius parameters r_V = r_I = 1.40 fm were used in the      
  calculation.                                                    
                                                                  
3. Level scheme of Y - 89                                         
  Nuclear discrete levels were obtained from RIPL-2/11/.          
  Contribution of the direct process was calculated by DWBA       
  for the levels marked with '*'.                                 
  ------------------------------------------------                
   No.   Ex(MeV)     J  PI           DWBA                         
  ------------------------------------------------                
    0    0.00000    1/2  -                                        
    1    0.90897    9/2  +                                        
    2    1.50726    3/2  -   * (l=2, beta=0.0470)                 
    3    1.74457    5/2  -   * (l=2, beta=0.0577)                 
    4    2.22239    5/2  +   * (l=3, beta=0.1001)                 
    5    2.52987    7/2  +   * (l=3, beta=0.1023)                 
    6    2.56624   11/2  +                                        
    7    2.62204    9/2  +                                        
    8    2.87180    7/2  +                                        
    9    2.88120    3/2  -                                        
   10    2.89470   13/2  +                                        
   11    3.06760    3/2  -                                        
   12    3.10706    5/2  -                                        
   13    3.13890    5/2  -                                        
   14    3.24750    1/2  +                                        
   15    3.34308   13/2  +                                        
   16    3.41050    5/2  +                                        
   17    3.45120    5/2  +                                        
   18    3.50360    1/2  -                                        
   19    3.51560    5/2  -                                        
   20    3.55710    7/2  -                                        
   21    3.56000    1/2  +                                        
   22    3.62100    5/2  -                                        
   23    3.63030   11/2  +                                        
   24    3.71530    5/2  +                                        
   25    3.74770   11/2  +                                        
   26    3.75270    5/2  +                                        
   27    3.84810    7/2  -                                        
   28    3.86230    5/2  -                                        
   29    3.92400    7/2  -                                        
   30    3.97690    9/2  +                                        
   31    3.99160    3/2  -                                        
   32    4.01530    1/2  +                                        
   33    4.02280    5/2  -                                        
  ------------------------------------------------                
  Levels above  4.03280 MeV are assumed to be continuous.         
                                                                  
4. Level density parameters                                       
 Energy-dependent parameters of Mengoni-Nakajima /12/ were used   
  ---------------------------------------------------             
  Nuclei    a*    Pair     T     E0    Ematch Elv_max             
          1/MeV   MeV     MeV    MeV    MeV    MeV                
  ---------------------------------------------------             
  Y - 90  10.454  0.000  0.865 -0.779  4.677  2.624               
  Y - 89  11.127  1.272  0.682  1.455  3.665  4.023               
  Y - 88  11.494  0.000  0.820 -1.352  5.191  1.596               
  Sr- 89  10.953  1.272  0.720  1.044  4.474  4.050               
  Sr- 88  11.473  2.558  0.785  1.929  6.625  5.199               
  Sr- 87  12.365  1.287  0.727  0.097  5.814  3.136               
  Rb- 87  10.916  1.287  0.895 -0.274  7.103  3.099               
  Rb- 86   9.930  0.000  0.984 -2.108  6.936  2.025               
  Rb- 85  10.704  1.302  0.909 -1.411  8.601  2.088               
  ---------------------------------------------------             
                                                                  
5. Gamma-ray strength functions                                   
   M1, E2: Standard Lorentzian (SLO)                              
   E1    : Standard Lorentzian (SLO) /13/                         
           The position and width parameters in the E1            
           radiation were taken from the tabulation of            
           Dietrich and Berman/14/.                               
                                                                  
6. Preequilibrium process                                         
   Preequilibrium is on for n, p, d, t, He-3, and alpha.          
                                                                  
   The single particle state density parameters were              
   6.923, 4.41, 5.50, 8.71, 6.383, 7.508, 6.359 MeV^(-1)          
   for Y-90, Y-89, Sr-89, Rb-86, Sr-88, Sr-87, and Rb-87.         
                                                                  
   Effects of the particle pickup (and knockout for alpha) were   
   estimated using the semi-empirical formulas by Kalbach/15/.    
   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 /14/).                                                    
                                                                  
References                                                        
 1) A.Ichihara et al., J.Nucl.Sci.Technol. 46, 252 (2009).        
 2) H.M.Agrawal et al., Nucl. Phys., A501, 18 (1989).             
 3) J.W.Boldeman et al., Nucl. Sci. Eng., 64, 744 (1977).         
 4) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999)               
     [in Japanese].                                               
 5) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 6) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003).      
 7) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974).           
 8) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization               
     Phenomena in Nuclear Reactions," p.682, The University       
     of Wisconsin Press (1971).                                   
 9) O.F.Lemos, Orsay Report, Series A, No.136 (1972).             
10) E.D.Arthur, P.G.Young, LA-8626-MS (1980).                     
11) T.Belgya et al., IAEA-TECDOC-1506 (2006).                     
12) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151         
     (1994).                                                      
13) M.Brink, Ph.D thesis, Oxford University, 1955.                
14) S.S.Dietrich, B.L.Berman, Atom. Data Nucl. Data Tables,       
     38, 199 (1988).                                              
15) C.Kalbach, Z. Phys. A283, 401 (1977).