38-Sr- 87

 38-Sr- 87 JAEA       EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda 
                      DIST-MAY10                       20091127   
----JENDL-4.0         MATERIAL 3834                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda.        
09-10 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           
      Resolved resonance region (MLBW formula) : below 14.08 keV  
      Evaluation of JENDL-2 was performed on the basis of the     
      measurements by Camarda et al./1/ and Musgrove et al./2/    
      Neutron widths were derived from the data of 2g*(neutron    
      width) and neutron capture areas.  Neutron orbital angular  
      momentum L was assumed to be 0 for all resonance levels     
      except the 2nd level (L=1) at 35.27 eV.  However, the values
      of total spin J were unknown for all resonance levels. Thus,
      target spin of 4.5 was adopted as J value.  Average         
      radiation width of 180.4 meV was obtained by averaging the  
      given radiation widths.  hHwever, this value was reduced to 
      110.72 meV so as to reproduce the neutron capture resonance 
      integral of 118+-30 barns given by Mughabghab et al./3/     
      A negative resonance was also added at -50 eV, and the      
      parameters were adjusted so as to reproduce the thermal     
      capture cross section of 16+-3 barns given by Mughabghab et 
      al.                                                         
      For JENDL-3, the values of total spin J were tentatively    
      estimated with a random number method.  Neutron widths were 
      modified on the basis of the estimated J-values.  Radiation 
      width of the negative level was slightly adjusted so as to  
      reproduce the thermal capture cross section according to the
      modification of the positive levels.  Scattering radius was 
      taken from the graph (fig. 1, Part A) given by Mughabghab et
      al.                                                         
      In JENDL-4, the radiation width of the negative resonance   
      was changed to 145 meV.                                     
    Unresolved resonance region: 14.08 keV - 1 MeV                
      The parameters were obtained by fitting to the total and    
      capture cross sections calculated from POD /4/.  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           2.3975E+01                                   
     Elastic         6.9382E+00                                   
     n,gamma         1.7037E+01           1.2139E+02              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
MF= 3 Neutron cross sections                                      
  MT=  1 Total cross section                                      
    Calculated with POD code /4/.                                 
                                                                  
  MT=  2 Elastic scattering cross section                         
    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 /4/.                                 
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with POD code /4/.                                 
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with POD code /4/.                                 
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with POD code /4/.                                 
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with POD code /4/.                                 
                                                                  
  MT=102 Capture cross section                                    
    Calculated with POD code /4/.                                 
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with POD code /4/.                                 
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with POD code /4/.                                 
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with POD code /4/.                                 
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with POD code /4/.                                 
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with POD code /4/.                                 
                                                                  
  MT=203 (n,xp) cross section                                     
    Calculated with POD code /4/.                                 
                                                                  
  MT=204 (n,xd) cross section                                     
    Calculated with POD code /4/.                                 
                                                                  
  MT=205 (n,xt) cross section                                     
    Calculated with POD code /4/.                                 
                                                                  
  MT=206 (n,xHe3) cross section                                   
    Calculated with POD code /4/.                                 
                                                                  
  MT=207 (n,xa) cross section                                     
    Calculated with POD code /4/.                                 
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with POD code /4/.                                 
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Neutron spectra calculated with POD/4/.                       
                                                                  
  MT= 22 (n,na) reaction                                          
    Neutron spectra calculated with POD/4/.                       
                                                                  
  MT= 28 (n,np) reaction                                          
    Neutron spectra calculated with POD/4/.                       
                                                                  
  MT= 32 (n,nd) reaction                                          
    Neutron spectra calculated with POD/4/.                       
                                                                  
  MT= 51 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 52 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 53 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 54 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 55 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 56 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 57 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 58 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 59 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 60 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 61 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 62 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 63 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 64 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 65 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 66 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 67 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 68 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 69 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 70 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 71 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 72 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 91 (n,n') reaction                                          
    Neutron spectra calculated with POD/4/.                       
                                                                  
  MT= 203 (n,xp) reaction                                         
    Proton spectra calculated with POD/4/.                        
                                                                  
  MT= 204 (n,xd) reaction                                         
    Deuteron spectra calculated with POD/4/.                      
                                                                  
  MT= 205 (n,xt) reaction                                         
    Triton spectra calculated with POD/4/.                        
                                                                  
  MT= 206 (n,xHe3) reaction                                       
    He3 spectra calculated with POD/4/.                           
                                                                  
  MT= 207 (n,xa) reaction                                         
    Alpha spectra calculated with POD/4/.                         
                                                                  
MF=12 Gamma-ray multiplicities                                    
  MT=  3 Non-elastic gamma emission                               
    Calculated with POD code /4/.                                 
                                                                  
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 /4/.                                 
                                                                  
                                                        
                                                                  
***************************************************************   
*        Nuclear Model Calculations with POD Code /4/         *   
***************************************************************   
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 /5/                    
Protons:                                                          
  Koning and Delaroche /6/                                        
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/          
                                                                  
3. Level scheme of Sr- 87                                         
  -------------------------                                       
   No.   Ex(MeV)     J  PI                                        
  -------------------------                                       
    0    0.00000    9/2  +                                        
    1    0.38853    1/2  -                                        
    2    0.87334    3/2  -                                        
    3    1.22842    5/2  +                                        
    4    1.25395    5/2  -                                        
    5    1.74000   13/2  +                                        
    6    1.74200    3/2  +                                        
    7    1.77047    5/2  +                                        
    8    1.92049    7/2  +                                        
    9    2.11006    3/2  -                                        
   10    2.15350   11/2  +                                        
   11    2.16941    1/2  +                                        
   12    2.23570    7/2  +                                        
   13    2.26200    3/2  -                                        
   14    2.41452    3/2  -                                        
   15    2.42040    7/2  -                                        
   16    2.48800    7/2  -                                        
   17    2.53280    9/2  +                                        
   18    2.53630   11/2  -                                        
   19    2.53900    7/2  -                                        
   20    2.55000    7/2  +                                        
   21    2.55500    9/2  -                                        
   22    2.59600   13/2  -                                        
  -------------------------                                       
  Levels above  2.60600 MeV are assumed to be continuous.         
                                                                  
4. Level density parameters                                       
 Energy-dependent parameters of Mengoni-Nakajima /11/ were used   
  ----------------------------------------------------------      
  Nuclei    a*    Pair    Esh     T     E0    Ematch Elv_max      
          1/MeV   MeV     MeV    MeV    MeV    MeV    MeV         
  ----------------------------------------------------------      
  Sr- 88  11.476  2.558 -1.509  0.753  2.134  6.189  4.515        
  Sr- 87  12.367  1.287 -0.021  0.633  0.786  4.453  2.596        
  Sr- 86  11.310  2.588  0.767  0.818  0.770  8.345  3.056        
  Sr- 85  11.114  1.302  1.863  0.862 -1.338  8.278  1.794        
  Rb- 87  10.932  1.287 -0.777  0.871 -0.070  6.722  2.414        
  Rb- 86   9.932  0.000  0.007  0.898 -1.348  5.547  1.738        
  Rb- 85  10.720  1.302  1.529  0.855 -0.855  7.650  2.088        
  Kr- 85  11.890  1.302  0.718  0.695  0.285  5.433  2.637        
  Kr- 84  11.089  2.619  1.235  0.745  1.364  7.286  3.951        
  Kr- 83  11.668  1.317  2.381  0.710 -0.316  6.290  1.889        
  ----------------------------------------------------------      
                                                                  
5. Gamma-ray strength functions                                   
   M1, E2: Standard Lorentzian (SLO)                              
   E1    : Generalized Lorentzian (GLO) /12/                      
                                                                  
6. Preequilibrium process                                         
   Preequilibrium is on for n, p, d, t, He-3, and alpha.          
   Preequilibrium capture is on.                                  
                                                                  
References                                                        
 1) H.Camarda et al., NCSAC-31, 40 (1970).                        
 2) A.R.de L.Musgrove et al., Proc. Int. Conf. on Neutron         
    Physics and Nucl. Data for Reactors, Harwell 1978, 449.       
 3) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I,       
    Part A", Academic Press (1981).                               
 4) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007).            
 5) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (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) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151         
    (1994).                                                       
12) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).