38-Sr- 88

 38-Sr- 88 JAEA       EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda 
                      DIST-JAN15                       20140703   
----JENDL-4.0u1       MATERIAL 3837                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
Update File Distribution                                          
Jan.22,2015 JENDL-4.0u1                                           
                                                                  
History                                                           
09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda.        
09-11 Compiled by K. Shibata.                                     
14-07 It was found that some of the neutron widths in the resolved
      resonances were underestimated mistakenly and that the      
      265.06-keV resonance was not considered.  Modification was  
      made to resolve these problems.  Moreover, the gamma width  
      at a negative resonance was re-adjusted.                    
                                                                  
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 300 keV       
      Resolved resonance parameters were taken from the work of   
      Koehler et al./1/  The new evaluation does not contains     
      the resonances at 2.780 keV and 12.70 keV which existed in  
      JENDL-3.3.  The former resonance, which were observed only  
      by Adamchuk et al./2/, is possibly attributed to Sr-87.     
      A negative resonance was added so as to reproduce the       
      thermal capture cross section recommended by Mughabghab.    
      /3/                                                         
    Unresolved resonance region: 300 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           5.5994E+00                                   
     Elastic         5.5936E+00                                   
     n,gamma         5.8014E-03           3.1278E-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=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= 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= 73 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 74 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 75 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 76 (n,n') reaction                                          
    Neutron angular distributions calculated with POD/4/.         
                                                                  
  MT= 77 (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- 88                                         
  -------------------------                                       
   No.   Ex(MeV)     J  PI                                        
  -------------------------                                       
    0    0.00000     0   +                                        
    1    1.83609     2   +                                        
    2    2.73414     3   -                                        
    3    3.15200     0   +                                        
    4    3.21851     2   +                                        
    5    3.48656     2   +                                        
    6    3.52294     2   +                                        
    7    3.58478     5   -                                        
    8    3.63511     2   +                                        
    9    3.95264     5   -                                        
   10    3.99300     1   -                                        
   11    4.01964     5   -                                        
   12    4.03560     2   +                                        
   13    4.03907     2   +                                        
   14    4.17042     3   -                                        
   15    4.17100     6   +                                        
   16    4.22410     4   +                                        
   17    4.22724     3   +                                        
   18    4.26871     2   +                                        
   19    4.29966     4   +                                        
   20    4.35500     1   -                                        
   21    4.36824     7   -                                        
   22    4.41395     2   +                                        
   23    4.44077     5   +                                        
   24    4.45202     4   +                                        
   25    4.48500     0   +                                        
   26    4.51402     2   -                                        
   27    4.51453     3   +                                        
  -------------------------                                       
  Levels above  4.52453 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- 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        
  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        
  Rb- 88  10.406  0.000 -0.431  0.771 -0.492  3.809  1.916        
  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        
  Kr- 86  11.310  2.588 -0.507  0.715  2.085  6.130  3.575        
  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        
  ----------------------------------------------------------      
                                                                  
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) P.E.Koehler et al., Phys. Rev., C62, 055803 (2000).           
 2) Yu.V.Adamchuk et al., Euoronuclear 2, 183 (1965).             
 3) S.F.Mughabghab, "Atlas of Neutron Resonances", Elsevier       
   (2006).                                                        
 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).