38-Sr- 90

 38-Sr- 90 JAEA       EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda 
                      DIST-MAY10                       20091126   
----JENDL-4.0         MATERIAL 3843                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda.        
09-11 Compiled by K. Shibata.                                     
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2 Resonance parameters                                        
  MT=151 Resolved and unresolved resonance parameters             
    No resolved resonance parameters are given.                   
      The constant elastic scattering  and 1/v-shaped capture     
      cross sections are assumed below 6 keV.  The scattering     
      cross section was taken from JENDL-3.3, i.e., 5.8037 b.     
      The capture cross section was normalized to the value of    
      10.1 mb measured by Nakamura et al./1/                      
    Unresolved resonance region: 6 keV - 1 MeV                    
      The parameters were obtained by fitting to the total and    
      capture cross sections calculated from POD /2/.  The        
      unresolved 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           5.8475E+00                                   
     Elastic         5.8390E+00                                   
     n,gamma         1.0105E-02           8.6013E-02              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    Sum of elastic and non-elastic cross sections below 6 keV.    
    Calculated with POD code /2/ above 6 keV.                     
                                                                  
  MT=  2 Elastic scattering cross section                         
    A value of 5.8037 b was adopted below 6 keV.  The cross       
    section was obtained by subtracting non-elastic cross         
    sections from total cross sections.                           
                                                                  
  MT=  3 Non-elastic cross section                                
    Sum of partial non-elastic cross sections.                    
                                                                  
  MT=  4,51-91 (n,n') cross section                               
    Calculated with POD code /2/.                                 
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT=102 Capture cross section                                    
    Calculated with POD code /2/ above 6 keV.  The 1/v-shaped     
    cross section is assumed below 6 keV.                         
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with POD code /2/.                                 
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with POD code /2/.                                 
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with POD code /2/.                                 
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with POD code /2/.                                 
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with POD code /2/.                                 
                                                                  
  MT=203 (n,xp) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT=204 (n,xd) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT=205 (n,xt) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
  MT=206 (n,xHe3) cross section                                   
    Calculated with POD code /2/.                                 
                                                                  
  MT=207 (n,xa) cross section                                     
    Calculated with POD code /2/.                                 
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with POD code /2/.                                 
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 17 (n,3n) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 32 (n,nd) reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 51 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 52 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 53 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 54 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 55 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 56 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 57 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 58 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 59 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 60 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 61 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 62 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 63 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 64 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 65 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 66 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 67 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 68 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 69 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 70 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/2/.         
                                                                  
  MT= 91 (n,n') reaction                                          
    Neutron spectra calculated with POD/2/.                       
                                                                  
  MT= 203 (n,xp) reaction                                         
    Proton spectra calculated with POD/2/.                        
                                                                  
  MT= 204 (n,xd) reaction                                         
    Deuteron spectra calculated with POD/2/.                      
                                                                  
  MT= 205 (n,xt) reaction                                         
    Triton spectra calculated with POD/2/.                        
                                                                  
  MT= 206 (n,xHe3) reaction                                       
    He3 spectra calculated with POD/2/.                           
                                                                  
  MT= 207 (n,xa) reaction                                         
    Alpha spectra calculated with POD/2/.                         
                                                                  
MF=12 Gamma-ray multiplicities                                    
  MT=  3 Non-elastic gamma emission                               
    Calculated with POD code /2/.                                 
                                                                  
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 /2/.                                 
                                                                  
                                                        
                                                                  
***************************************************************   
*        Nuclear Model Calculations with POD Code /2/         *   
***************************************************************   
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:                                                         
  Coupled-channel optical model parameters /3/                    
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 Sr- 90                                         
  -------------------------                                       
   No.   Ex(MeV)     J  PI                                        
  -------------------------                                       
    0    0.00000     0   +                                        
    1    0.83168     2   +                                        
    2    1.65591     4   +                                        
    3    1.89236     2   +                                        
    4    2.20702     3   -                                        
    5    2.49732     2   +                                        
    6    2.52792     4   +                                        
    7    2.57060     0   +                                        
    8    2.58600     2   +                                        
    9    2.67400     0   +                                        
   10    2.92770     2   -                                        
   11    2.97112     0   +                                        
   12    3.03287     0   +                                        
   13    3.03800     1   +                                        
   14    3.03926     2   +                                        
   15    3.14490     2   +                                        
   16    3.14600     5   -                                        
   17    3.26800     3   -                                        
   18    3.38339     1   +                                        
   19    3.39400     1   +                                        
   20    3.44982     4   +                                        
  -------------------------                                       
  Levels above  3.45982 MeV are assumed to be continuous.         
                                                                  
4. Level density parameters                                       
 Energy-dependent parameters of Mengoni-Nakajima /9/ were used    
  ----------------------------------------------------------      
  Nuclei    a*    Pair    Esh     T     E0    Ematch Elv_max      
          1/MeV   MeV     MeV    MeV    MeV    MeV    MeV         
  ----------------------------------------------------------      
  Sr- 91  12.552  1.258  0.619  0.586  0.839  4.128  2.159        
  Sr- 90  11.750  2.530  0.151  0.778  1.140  7.585  3.450        
  Sr- 89  10.955  1.272 -0.954  0.720  1.043  4.477  3.524        
  Sr- 88  11.476  2.558 -1.509  0.753  2.134  6.189  4.515        
  Rb- 90  11.714  0.000  0.853  0.721 -1.164  4.492  0.741        
  Rb- 89  11.144  1.272  0.815  0.775 -0.065  6.238  1.999        
  Rb- 88  10.406  0.000 -0.431  0.771 -0.492  3.809  1.916        
  Kr- 88  11.530  2.558  0.766  0.778  1.012  7.795  3.608        
  Kr- 87  12.111  1.287 -0.112  0.649  0.793  4.518  3.172        
  Kr- 86  11.310  2.588 -0.507  0.715  2.085  6.130  3.575        
  ----------------------------------------------------------      
                                                                  
5. Gamma-ray strength functions                                   
   M1, E2: Standard Lorentzian (SLO)                              
   E1    : Generalized Lorentzian (GLO) /10/                      
                                                                  
6. Preequilibrium process                                         
   Preequilibrium is on for n, p, d, t, He-3, and alpha.          
   Preequilibrium capture is on.                                  
                                                                  
References                                                        
 1) S.Nakamura et al., J. Nucl. Sci. Technol., 38, 1029 (2007).   
 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (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) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151         
    (1994).                                                       
10) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).